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Sample records for radiological dose assessments

  1. Dose assessment in radiological accidents

    International Nuclear Information System (INIS)

    Donkor, S.

    2013-04-01

    The applications of ionizing radiation bring many benefits to humankind, ranging from power generation to uses in medicine, industry and agriculture. Facilities that use radiation source require special care in the design and operation of equipment to prevent radiation injury to workers or to the public. Despite considerable development of radiation safety, radiation accidents do happen. The purpose of this study is therefore to discuss how to assess doses to people who will be exposed to a range of internal and external radiation sources in the event of radiological accidents. This will go a long way to complement their medical assessment thereby helping to plan their treatment. Three radiological accidents were reviewed to learn about the causes of those accidents and the recommendations that were put in place to prevent recurrence of such accidents. Various types of dose assessment methods were discussed.(au)

  2. A radiological dose assessment for the Port Hope conversion facility

    International Nuclear Information System (INIS)

    Garisto, N.C.; Cooper, F.; Janes, A.; Stager, R.; Peters, R.

    2011-01-01

    The Port Hope Conversion Facility (PHCF) receives uranium trioxide for conversion to uranium hexafluoride (UF 6 ) or uranium dioxide (UO 2 ). The PHCF Site has a long history of industrial use. A Radiological Dose Assessment was undertaken as part of a Site Wide Risk Assessment. This assessment took into account all possible human receptors, both workers and members of the public. This paper focuses on a radiological assessment of dose to members of the public. The doses to members of the public from terrestrial pathways were added to the doses from aquatic pathways to obtain overall dose to receptors. The benchmark used in the assessment is 1 mSv/y. The estimated doses related to PHCF operations are much lower than the dose limit. (author)

  3. Radiological assessment. A textbook on environmental dose analysis

    International Nuclear Information System (INIS)

    Till, J.E.; Meyer, H.R.

    1983-09-01

    Radiological assessment is the quantitative process of estimating the consequences to humans resulting from the release of radionuclides to the biosphere. It is a multidisciplinary subject requiring the expertise of a number of individuals in order to predict source terms, describe environmental transport, calculate internal and external dose, and extrapolate dose to health effects. Up to this time there has been available no comprehensive book describing, on a uniform and comprehensive level, the techniques and models used in radiological assessment. Radiological Assessment is based on material presented at the 1980 Health Physics Society Summer School held in Seattle, Washington. The material has been expanded and edited to make it comprehensive in scope and useful as a text. Topics covered include (1) source terms for nuclear facilities and Medical and Industrial sites; (2) transport of radionuclides in the atmosphere; (3) transport of radionuclides in surface waters; (4) transport of radionuclides in groundwater; (5) terrestrial and aquatic food chain pathways; (6) reference man; a system for internal dose calculations; (7) internal dosimetry; (8) external dosimetry; (9) models for special-case radionuclides; (10) calculation of health effects in irradiated populations; (11) evaluation of uncertainties in environmental radiological assessment models; (12) regulatory standards for environmental releases of radionuclides; (13) development of computer codes for radiological assessment; and (14) assessment of accidental releases of radionuclides

  4. Radiological assessment. A textbook on environmental dose analysis

    Energy Technology Data Exchange (ETDEWEB)

    Till, J.E.; Meyer, H.R. (eds.)

    1983-09-01

    Radiological assessment is the quantitative process of estimating the consequences to humans resulting from the release of radionuclides to the biosphere. It is a multidisciplinary subject requiring the expertise of a number of individuals in order to predict source terms, describe environmental transport, calculate internal and external dose, and extrapolate dose to health effects. Up to this time there has been available no comprehensive book describing, on a uniform and comprehensive level, the techniques and models used in radiological assessment. Radiological Assessment is based on material presented at the 1980 Health Physics Society Summer School held in Seattle, Washington. The material has been expanded and edited to make it comprehensive in scope and useful as a text. Topics covered include (1) source terms for nuclear facilities and Medical and Industrial sites; (2) transport of radionuclides in the atmosphere; (3) transport of radionuclides in surface waters; (4) transport of radionuclides in groundwater; (5) terrestrial and aquatic food chain pathways; (6) reference man; a system for internal dose calculations; (7) internal dosimetry; (8) external dosimetry; (9) models for special-case radionuclides; (10) calculation of health effects in irradiated populations; (11) evaluation of uncertainties in environmental radiological assessment models; (12) regulatory standards for environmental releases of radionuclides; (13) development of computer codes for radiological assessment; and (14) assessment of accidental releases of radionuclides.

  5. Development of a real-time radiological dose assessment system

    Energy Technology Data Exchange (ETDEWEB)

    Han, Moon Hee; Lee, Young Bok; Kim, Eun Han; Suh, Kyung Suk; Hwang, Won Tae; Choi, Young Gil

    1997-07-01

    A radiological dose assessment system named FADAS has been developed. This system is necessary to estimated the radiological consequences against a nuclear accident. Mass-consistent wind field module was adopted for the generation of wind field over the whole domain using the several measured wind data. Random-walk dispersion module is used for the calculation of the distribution of radionuclides in the atmosphere. And volume-equivalent numerical integration method has been developed for the assessment of external gamma exposure given from a randomly distributed radioactive materials and a dose data library has been made for rapid calculation. Field tracer experiments have been carried out for the purpose of analyzing the site-specific meteorological characteristics and increasing the accuracy of wind field generation and atmospheric dispersion module of FADAS. At first, field tracer experiment was carried out over flat terrain covered with rice fields using the gas samplers which were designed and manufactured by the staffs of KAERI. The sampled gas was analyzed using gas chromatograph. SODAR and airsonde were used to measure the upper wind. Korean emergency preparedness system CARE was integrated at Kori 4 nuclear power plants in 1995. One of the main functions of CARE is to estimate the radiological dose. The developed real-time dose assessment system FADAS was adopted in CARE as a tool for the radiological dose assessment. (author). 79 refs., 52 tabs., 94 figs.

  6. A model for radiological dose assessment in an urban environment

    International Nuclear Information System (INIS)

    Hwang, Won Tae; Kim, Eun Han; Jeong, Hyo Joon; Suh, Kyung Suk; Han, Moon Hee

    2007-01-01

    A model for radiological dose assessment in an urban environment, METRO-K has been developed. Characteristics of the model are as follows ; 1) mathematical structures are simple (i.e. simplified input parameters) and easy to understand due to get the results by analytical methods using experimental and empirical data, 2) complex urban environment can easily be made up using only 5 types of basic surfaces, 3) various remediation measures can be applied to different surfaces by evaluating the exposure doses contributing from each contamination surface. Exposure doses contributing from each contamination surface at a particular location of a receptor were evaluated using the data library of kerma values as a function of gamma energy and contamination surface. A kerma data library was prepared for 7 representative types of Korean urban building by extending those data given for 4 representative types of European urban buildings. Initial input data are daily radionuclide concentration in air and precipitation, and fraction of chemical type. Final outputs are absorbed dose rate in air contributing from the basic surfaces as a function of time following a radionuclide deposition, and exposure dose rate contributing from various surfaces constituting the urban environment at a particular location of a receptor. As the result of a contaminative scenario for an apartment built-up area, exposure dose rates show a distinct difference for surrounding environment as well as locations of a receptor

  7. TSD-DOSE : a radiological dose assessment model for treatment, storage, and disposal facilities

    International Nuclear Information System (INIS)

    Pfingston, M.

    1998-01-01

    In May 1991, the U.S. Department of Energy (DOE), Office of Waste Operations, issued a nationwide moratorium on shipping slightly radioactive mixed waste from DOE facilities to commercial treatment, storage, and disposal (TSD) facilities. Studies were subsequently conducted to evaluate the radiological impacts associated with DOE's prior shipments through DOE's authorized release process under DOE Order 5400.5. To support this endeavor, a radiological assessment computer code--TSD-DOSE (Version 1.1)--was developed and issued by DOE in 1997. The code was developed on the basis of detailed radiological assessments performed for eight commercial hazardous waste TSD facilities. It was designed to utilize waste-specific and site-specific data to estimate potential radiological doses to on-site workers and the off-site public from waste handling operations at a TSD facility. The code has since been released for use by DOE field offices and was recently used by DOE to evaluate the release of septic waste containing residual radioactive material to a TSD facility licensed under the Resource Conservation and Recovery Act. Revisions to the code were initiated in 1997 to incorporate comments received from users and to increase TSD-DOSE's capability, accuracy, and flexibility. These updates included incorporation of the method used to estimate external radiation doses from DOE's RESRAD model and expansion of the source term to include 85 radionuclides. In addition, a detailed verification and benchmarking analysis was performed

  8. The Northern Marshall Islands radiological survey: Data and dose assessments

    International Nuclear Information System (INIS)

    Robison, W.L.; Noshkin, V.E.; Conrado, C.L.

    1997-01-01

    Fallout from atmospheric nuclear tests, especially from those conducted at the Pacific Proving Grounds between 1946 and 1958, contaminated areas of the Northern Marshall Islands. A radiological survey at some Northern Marshall Islands was conducted from September through November 1978 to evaluate the extent of residual radioactive contamination. The atolls included in the Northern Marshall Islands Radiological Survey (NMIRS) were Likiep, Ailuk, Utirik, Wotho, Ujelang, Taka, Rongelap, Rongerik, Bikar, Ailinginae, and Mejit and Jemo Islands. The original test sites, Bikini and Enewetak Atolls, were also visited on the survey. An aerial survey was conducted to determine the external gamma exposure rate. Terrestrial (soil, food crops, animals, and native vegetation), cistern and well water samples, and marine (sediment, seawater, fish and clams) samples were collected to evaluate radionuclide concentrations in the atoll environment. Samples were processed and analyzed for 137 Cs, 90 Sr, 239+240 Pu and 241 Am. The dose from the ingestion pathway was calculated using the radionuclide concentration data and a diet model for local food, marine, and water consumption. The ingestion pathway contributes 70% to 90% of the estimated dose. Approximately 95% of the dose is from 137 Cs accounts for about 10% to 30% of the dose. 239+240 Pu and 241 Am are the major contributors to dose via the inhalation pathway; however, inhalation accounts for only about 1% of the total estimated dose, based on surface soil levels and resuspension studies. All doses are computed for concentrations decay corrected to 1996. The maximum annual effective dose from manmade radionuclides at these atolls ranges from .02 mSv y -1 . The background dose in the Marshall Islands is estimated to be 2.4 mSv y -1 to 4.5 mSv y -1 . The 50-y integral dose ranges from 0.5 to 65 mSv. 35 refs., 2 figs., 9 tabs

  9. TSD-DOSE: A radiological dose assessment model for treatment, storage, and disposal facilities

    International Nuclear Information System (INIS)

    Pfingston, M.; Arnish, J.; LePoire, D.; Chen, S.-Y.

    1998-01-01

    Past practices at US Department of Energy (DOE) field facilities resulted in the presence of trace amounts of radioactive materials in some hazardous chemical wastes shipped from these facilities. In May 1991, the DOE Office of Waste Operations issued a nationwide moratorium on shipping all hazardous waste until procedures could be established to ensure that only nonradioactive hazardous waste would be shipped from DOE facilities to commercial treatment, storage, and disposal (TSD) facilities. To aid in assessing the potential impacts of shipments of mixed radioactive and chemically hazardous wastes, a radiological assessment computer model (or code) was developed on the basis of detailed assessments of potential radiological exposures and doses for eight commercial hazardous waste TSD facilities. The model, called TSD-DOSE, is designed to incorporate waste-specific and site-specific data to estimate potential radiological doses to on-site workers and the off-site public from waste-handling operations at a TSD facility. The code is intended to provide both DOE and commercial TSD facilities with a rapid and cost-effective method for assessing potential human radiation exposures from the processing of chemical wastes contaminated with trace amounts of radionuclides

  10. The Northern Marshall Islands Radiological Survey: data and dose assessments.

    Science.gov (United States)

    Robison, W L; Noshkin, V E; Conrado, C L; Eagle, R J; Brunk, J L; Jokela, T A; Mount, M E; Phillips, W A; Stoker, A C; Stuart, M L; Wong, K M

    1997-07-01

    Fallout from atmospheric nuclear tests, especially from those conducted at the Pacific Proving Grounds between 1946 and 1958, contaminated areas of the Northern Marshall Islands. A radiological survey at some Northern Marshall Islands was conducted from September through November 1978 to evaluate the extent of residual radioactive contamination. The atolls included in the Northern Marshall Islands Radiological Survey (NMIRS) were Likiep, Ailuk, Utirik, Wotho, Ujelang, Taka, Rongelap, Rongerik, Bikar, Ailinginae, and Mejit and Jemo Islands. The original test sites, Bikini and Enewetak Atolls, were also visited on the survey. An aerial survey was conducted to determine the external gamma exposure rate. Terrestrial (soil, food crops, animals, and native vegetation), cistern and well water samples, and marine (sediment, seawater, fish and clams) samples were collected to evaluate radionuclide concentrations in the atoll environment. Samples were processed and analyzed for 137Cs, 90Sr, 239+240Pu and 241Am. The dose from the ingestion pathway was calculated using the radionuclide concentration data and a diet model for local food, marine, and water consumption. The ingestion pathway contributes 70% to 90% of the estimated dose. Approximately 95% of the dose is from 137Cs. 90Sr is the second most significant radionuclide via ingestion. External gamma exposure from 137Cs accounts for about 10% to 30% of the dose. 239+240Pu and 241Am are the major contributors to dose via the inhalation pathway; however, inhalation accounts for only about 1% of the total estimated dose, based on surface soil levels and resuspension studies. All doses are computed for concentrations decay corrected to 1996. The maximum annual effective dose from manmade radionuclides at these atolls ranges from .02 mSv y(-1) to 2.1 mSv y(-1). The background dose in the Marshall Islands is estimated to be 2.4 mSv y(-1). The combined dose from both background and bomb related radionuclides ranges from slightly

  11. Specific gamma-ray dose constants for nuclides important to dosimetry and radiological assessment

    International Nuclear Information System (INIS)

    Unger, L.M.; Trubey, D.K.

    1982-05-01

    Tables of specific gamma-ray dose constants (the unshielded gamma-ray dose equivalent rate at 1 m from a point source) have been computed for approximately 500 nuclides important to dosimetry and radiological assessment. The half life, the mean attenuation coefficient, and thickness for a lead shield providing 95% dose equivalent attenuation are also listed

  12. Facial exposure dose assessment during intraoral radiography by radiological technologists

    Energy Technology Data Exchange (ETDEWEB)

    Yu, Hwan; Yang, Han Joon [Dept. of International Radiological Science, Hallym University of Graduate Studies, Chuncheon (Korea, Republic of)

    2014-09-15

    The study examined the changes in the decreased facial exposure dose for radiological technologists depending on increased distance between the workers and the X-ray tube head during intraoral radiography. First, the facial phantom similar to the human tissues was manufactured. The shooting examination was configured to the maxillary molars for adults (60 kVp, 10 mA, 50 msec) and for children (60 kVp, 10 mA, 20 msec), and the chamber was fixed where the facial part of the radiation worker would be placed using the intraoral radiography equipment. The distances between the X-ray tube head and the phantom were set to 10 cm, 15 cm, 20 cm, 25 cm, 30 cm, 35 cm, and 40 cm. The phantom was radiated 20 times with each examination condition and the average scattered doses were examined. The rate at the distance of 40 cm decreased by about 92.6% to 7.43% based on the scattered rays radiated at the distance of 10 cm under the adult conditions. The rate at the distance of 40 cm decreased by about 97.6% to 2.58% based on the scattered rays radiated at the distance of 10 cm under the children conditions. Protection from the radiation exposure was required during the dental radiographic examination.

  13. Radiological dose assessment from the operation of Daeduk nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Won Tae; Kim, Eun Han; Suh, Kyung Suk; Choi, Young Gil [Korea Atomic Energy Research Institute, Taejon (Korea)

    2000-02-01

    The objective of this project is to assure the public acceptance for nuclear facilities, and the environmental safety from the operation of Daeduk nuclear facilities, such as HANARO research reactor, nuclear fuel processing facilities and others. For identifying the integrity of their facilities, the maximum individual doses at the site boundary and on the areas with high population density were assessed. Also, the collective doses within radius 80 km from the site were assessed. The radiation impacts for residents around the site from the operation of Daeduk nuclear facilities in 1999 were neglectable. 8 refs., 10 figs., 27 tabs. (Author)

  14. Radiological dose assessment related to management of naturally occurring radioactive materials generated by the petroleum industry

    International Nuclear Information System (INIS)

    Smith, K.P.; Blunt, D.L.; Williams, G.P.; Tebes, C.L.

    1995-01-01

    A preliminary radiological dose assessment related to equipment decontamination, subsurface disposal, landspreading, equipment smelting, and equipment burial was conducted to address concerns regarding the presence of naturally occurring radioactive materials in production waste streams. The assessment evaluated the relative dose of these activities and included a sensitivity analysis of certain input parameters. Future studies and potential policy actions are recommended

  15. Assessing radiological impacts (exposures and doses) associated with the mining and milling of radioactive ores

    International Nuclear Information System (INIS)

    Williams, G.A.

    1990-01-01

    The basic units and concepts applicable to radiological assessment are presented. Data relevant to the assessment of radiological exposures from the mining and milling phases of uranium and thorium ores are discussed. As a guide to the assessment of environmental exposures to members of the public, concepts such as the critical group are defined. Environmental transport and exposure pathways are presented in general terms, together with a discussion of the use of mathematical models. The dose assessment procedures defined in the 1987 Code of Practice are described. 13 refs., 2 tabs., 1 fig

  16. Application of probabilistic quantitative ecological risk assessment to radiological dose

    International Nuclear Information System (INIS)

    Twining, J.; Ferris, J.; Copplestone, D.; Zinger, I.

    2004-01-01

    Probabilistic ERA is becoming more accepted and applied in evaluations of environmental impacts worldwide. In a previous paper we have shown that the process can be applied in practice to routine effluent releases from a nuclear facility. However, there are practical issues that need to be addressed prior to its regulatory application for criteria setting or for site-specific ERA. Among these issues are a) appropriate data selection for both exposure and dose-response input, because there is a need to carefully characterise and filter the available dose-response data for its ecological relevance, b) A coherent approach is required to the choice of exposure scenarios, and c) there are various questions associated with treatment of exposure to mixed nuclides. In this paper we will evaluate and discuss aspects of these issues, using an illustrative case study approach. (author)

  17. RASCAL [Radiological Assessment System for Consequence AnaLysis]: A screening model for estimating doses from radiological accidents

    International Nuclear Information System (INIS)

    Sjoreen, A.L.; Athey, G.F.; Sakenas, C.A.; McKenna, T.J.

    1988-01-01

    The Radiological Assessment System for Consequence AnaLysis (RASCAL) is a new MS-DOS-based dose assessment model which has been written for the US Nuclear Regulatory Commission for use during response to radiological emergencies. RASCAL is designed to provide crude estimates of the effects of an accident while the accident is in progress and only limited information is available. It has been designed to be very simple to use and to run quickly. RASCAL is unique in that it estimates the source term based on fundamental plant conditions and does not rely solely on release rate estimation (e.g., Ci/sec of I-131). Therefore, it can estimate consequences of accidents involving unmonitored pathways or projected failures. RASCAL will replace the older model, IRDAM. 6 refs

  18. Review on Population Projection Methodology for Radiological Dose Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Jang, M. S.; Kang, H. S.; Kim, S. R. [NESS, Daejeon (Korea, Republic of); Hwang, W. T. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Yang, Y. H. [KHNP, Daejeon (Korea, Republic of)

    2015-05-15

    Radiation environment report (RER), one of the essential documents in plant operating license or continuous operation license, includes population projection. Population estimates are utilized in determining the collective dose at the operation or restart time of nuclear power plant. Many population projection models are suggested and also under development. We carried out the sensitivity analysis on various population projection models to Daejeon city as a target. Daejeon city showed the increase or decrease in the cross-sectional population, because of the development of Sejong city, Doan new town and etc. We analyzed the population of Daejeon city using statistical ARIMA model and various simple population projection models. It is important to determine the population limit in Modified exponential model but it is not easy. Therefore, the various properties of the area such as the decrease and increase of population, new town development plan, social and natural environment change and etc., should be carefully reviewed to estimate the future population of any area.

  19. Review on Population Projection Methodology for Radiological Dose Assessment

    International Nuclear Information System (INIS)

    Jang, M. S.; Kang, H. S.; Kim, S. R.; Hwang, W. T.; Yang, Y. H.

    2015-01-01

    Radiation environment report (RER), one of the essential documents in plant operating license or continuous operation license, includes population projection. Population estimates are utilized in determining the collective dose at the operation or restart time of nuclear power plant. Many population projection models are suggested and also under development. We carried out the sensitivity analysis on various population projection models to Daejeon city as a target. Daejeon city showed the increase or decrease in the cross-sectional population, because of the development of Sejong city, Doan new town and etc. We analyzed the population of Daejeon city using statistical ARIMA model and various simple population projection models. It is important to determine the population limit in Modified exponential model but it is not easy. Therefore, the various properties of the area such as the decrease and increase of population, new town development plan, social and natural environment change and etc., should be carefully reviewed to estimate the future population of any area

  20. Radiation dose reduction: comparative assessment of publication volume between interventional and diagnostic radiology.

    Science.gov (United States)

    Hansmann, Jan; Henzler, Thomas; Gaba, Ron C; Morelli, John N

    2017-01-01

    We aimed to quantify and compare awareness regarding radiation dose reduction within the interventional radiology and diagnostic radiology communities. Abstracts accepted to the annual meetings of the Society of Interventional Radiology (SIR), the Cardiovascular and Interventional Radiological Society of Europe (CIRSE), the Radiological Society of North America (RSNA), and the European Congress of Radiology (ECR) between 2005 and 2015 were analyzed using the search terms "interventional/computed tomography" and "radiation dose/radiation dose reduction." A PubMed query using the above-mentioned search terms for the years of 2005-2015 was performed. Between 2005 and 2015, a total of 14 520 abstracts (mean, 660±297 abstracts) and 80 614 abstracts (mean, 3664±1025 abstracts) were presented at interventional and diagnostic radiology meetings, respectively. Significantly fewer abstracts related to radiation dose were presented at the interventional radiology meetings compared with the diagnostic radiology meetings (162 abstracts [1% of total] vs. 2706 [3% of total]; P radiology abstracts (range, 6-27) and 246±105 diagnostic radiology abstracts (range, 112-389) pertaining to radiation dose were presented at each meeting. The PubMed query revealed an average of 124±39 publications (range, 79-187) and 1205±307 publications (range, 829-1672) related to interventional and diagnostic radiology dose reduction per year, respectively (P radiology community over the past 10 years has not mirrored the increased volume seen within diagnostic radiology, suggesting that increased education and discussion about this topic may be warranted.

  1. Radiological dose assessment related to management of naturally occurring radioactive materials generated by the petroleum industry

    International Nuclear Information System (INIS)

    Smith, K.P.; Blunt, D.L.; Williams, G.P.

    1996-09-01

    A preliminary radiological dose assessment of equipment decontamination, subsurface disposal, landspreading, equipment smelting, and equipment burial was conducted to address concerns regarding the presence of naturally occurring radioactive materials (NORM) in production waste streams. The assessment estimated maximum individual dose equivalents for workers and the general public. Sensitivity analyses of certain input parameters also were conducted. On the basis of this assessment, it is concluded that (1) regulations requiring workers to wear respiratory protection during equipment cleaning operations are likely to result in lower worker doses, (2) underground injection and downhole encapsulation of NORM wastes present a negligible risk to the general public, and (3) potential doses to workers and the general public related to smelting NORM-contaminated equipment can be controlled by limiting the contamination level of the initial feed. It is recommended that (1) NORM wastes be further characterized to improve studies of potential radiological doses; (2) states be encouraged to permit subsurface disposal of NORM more readily, provided further assessments support this study; results; (3) further assessment of landspreading NORM wastes be conducted; and (4) the political, economic, sociological, and nonradiological issues related to smelting NORM-contaminated equipment be studied to fully examine the feasibility of this disposal option

  2. Assessment of eye lens doses for workers during interventional radiology procedures

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  3. Radiological Dose Calculations And Supplemental Dose Assessment Data For Neshap Compliance For SNL Nevada Facilities 1996.

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2017-05-01

    Operations of Sandia National Laboratories, Nevada (SNL/NV) at the Tonopah Test Range (TTR) resulted in no planned point radiological releases during 1996. Other releases from SNL/NV included diffuse transuranic sources consisting of the three Clean Slate sites. Air emissions from these sources result from wind resuspension of near-surface transuranic contaminated soil particulates. The total area of contamination has been estimated to exceed 20 million square meters. Soil contamination was documented in an aerial survey program in 1977 (EG&G 1979). Surface contamination levels were generally found to be below 400 pCi/g of combined plutonium-238, plutonium-239, plutonium-240, and americium-241 (i.e., transuranic) activity. Hot spot areas contain up to 43,000 pCi/g of transuranic activity. Recent measurements confirm the presence of significant levels of transuranic activity in the surface soil. An annual diffuse source term of 0.39 Ci of transuranic material was calculated for the cumulative release from all three Clean Slate sites. A maximally exposed individual dose of 1.1 mrem/yr at the TTR airport area was estimated based on the 1996 diffuse source release amounts and site-specific meteorological data. A population dose of 0.86 person-rem/yr was calculated for the local residents. Both dose values were attributable to inhalation of transuranic contaminated dust.

  4. Assessment of radiation protection awareness and knowledge about radiological examination doses among Italian radiographers.

    Science.gov (United States)

    Paolicchi, F; Miniati, F; Bastiani, L; Faggioni, L; Ciaramella, A; Creonti, I; Sottocornola, C; Dionisi, C; Caramella, D

    2016-04-01

    To evaluate radiation protection basic knowledge and dose assessment for radiological procedures among Italian radiographers A validated questionnaire was distributed to 780 participants with balanced demographic characteristics and geographic distribution. Only 12.1 % of participants attended radiation protection courses on a regular basis. Despite 90 % of radiographers stating to have sufficient awareness of radiation protection issues, most of them underestimated the radiation dose of almost all radiological procedures. About 5 % and 4 % of the participants, respectively, claimed that pelvis magnetic resonance imaging and abdominal ultrasound exposed patients to radiation. On the contrary, 7.0 % of the radiographers stated that mammography does not use ionising radiation. About half of participants believed that radiation-induced cancer is not dependent on age or gender and were not able to differentiate between deterministic and stochastic effects. Young radiographers (with less than 3 years of experience) showed a higher level of knowledge compared with the more experienced radiographers. There is a substantial need for radiographers to improve their awareness of radiation protection issues and their knowledge of radiological procedures. Specific actions such as regular training courses for both undergraduate and postgraduate students as well as for working radiographers must be considered in order to assure patient safety during radiological examinations. • Radiographers should improve their knowledge on radiation protection issues. • Only 12.1 % of participants attended radiation protection courses on a regular basis. • Specific actions must be considered in order to increase knowledge and awareness.

  5. Effective doses in paediatric radiology

    International Nuclear Information System (INIS)

    Iacob, Olga; Diaconescu, Cornelia; Roca, Antoaneta

    2001-01-01

    Because of their longer life expectancy, the risk of late manifestations of detrimental radiation effects is greater in children than in adults and, consequently, paediatric radiology gives ground for more concern regarding radiation protection than radiology of adults. The purpose of our study is to assess in terms of effective doses the magnitude of paediatric patient exposure during conventional X-ray examinations, selected for their high frequency or their relatively high doses to the patient. Effective doses have been derived from measurements of dose-area product (DAP) carried out on over 900 patients undergoing X-ray examinations, in five paediatric units. The conversion coefficients for estimating effective doses are those calculated by the NRPB using Monte-Carlo technique on a series of 5 mathematical phantoms representing 0, 1, 5, 10 and 15 year old children. The annual frequency of X-ray examinations necessary for collective dose calculation are those reported in our last national study on medical exposure, conducted in 1995. The annual effective doses from all medical examinations for the average paediatric patient are as follows: 1.05 mSv for 0 year old, 0.98 mSv for 1 year old, 0.53 mSv for 5 year old, 0.65 mSv for 10 year old and 0.70 mSv for 15 year old. The resulting annual collective effective dose was evaluated at 625 man Sv with the largest contribution of pelvis and hip examinations (34%). The annual collective effective associated with paediatric radiology in Romania represent 5% of the annual value resulting from all diagnostic radiology. Examination of the chest is by far the most frequent procedure for children, accounting for about 60 per cent of all annually performed X-ray conventional examinations. Knowledge of real level of patient dose is an essential component of quality assurance programs in paediatric radiology. (authors)

  6. SUDOQU, a new dose-assessment methodology for radiological surface contamination.

    Science.gov (United States)

    van Dillen, Teun; van Dijk, Arjan

    2018-06-12

    A new methodology has been developed for the assessment of the annual effective dose resulting from removable and fixed radiological surface contamination. It is entitled SUDOQU (SUrface DOse QUantification) and it can for instance be used to derive criteria for surface contamination related to the import of non-food consumer goods, containers and conveyances, e.g., limiting values and operational screening levels. SUDOQU imposes mass (activity)-balance equations based on radioactive decay, removal and deposition processes in indoor and outdoor environments. This leads to time-dependent contamination levels that may be of particular importance in exposure scenarios dealing with one or a few contaminated items only (usually public exposure scenarios, therefore referred to as the 'consumer' model). Exposure scenarios with a continuous flow of freshly contaminated goods also fall within the scope of the methodology (typically occupational exposure scenarios, thus referred to as the 'worker model'). In this paper we describe SUDOQU, its applications, and its current limitations. First, we delineate the contamination issue, present the assumptions and explain the concepts. We describe the relevant removal, transfer, and deposition processes, and derive equations for the time evolution of the radiological surface-, air- and skin-contamination levels. These are then input for the subsequent evaluation of the annual effective dose with possible contributions from external gamma radiation, inhalation, secondary ingestion (indirect, from hand to mouth), skin contamination, direct ingestion and skin-contact exposure. The limiting effective surface dose is introduced for issues involving the conservatism of dose calculations. SUDOQU can be used by radiation-protection scientists/experts and policy makers in the field of e.g. emergency preparedness, trade and transport, exemption and clearance, waste management, and nuclear facilities. Several practical examples are worked

  7. Radiological dose assessment of naturally occurring radioactive materials in concrete building materials

    International Nuclear Information System (INIS)

    Amran AB Majid; Aznan Fazli Ismail; Muhamad Samudi Yasir; Redzuwan Yahaya; Ismail Bahari

    2013-01-01

    Previous studies have shown that the natural radioactivity contained in building materials have significantly influenced the dose rates in dwelling. Exposure to natural radiation in building has been of concerned since almost 80 % of our daily live are spend indoor. Thus, the aim of the study is to assess the radiological risk associated by natural radioactivity in soil based building materials to dwellers. A total of 13 Portland cement, 46 sand and 43 gravel samples obtained from manufacturers or bought directly from local hardware stores in Peninsular of Malaysia were analysed for their radioactivity concentrations. The activity concentrations of 226 Ra, 232 Th and 40 K in the studied building materials samples were found to be in the range of 3.7-359.3, 2.0-370.8 and 10.3-1,949.5 Bq kg -1 respectively. The annual radiation dose rates (μSv year -1 ) received by dwellers were evaluated for 1 to 50 years of exposure using Resrad-Build Computer Code based on the activity concentration of 226 Ra, 232 Th and 40 K found in the studied building material samples. The rooms modelling were based on the changing parameters of concrete wall thickness and the room dimensions. The annual radiation dose rates to dwellers were found to increase annually over a period of 50 years. The concrete thicknesses were found to have significantly influenced the dose rates in building. The self-absorption occurred when the concrete thickness was thicker than 0.4 m. Results of this study shows that the dose rates received by the dwellers of the building are proportional to the size of the room. In general the study concludes that concrete building materials; Portland cements, sands, and gravels in Peninsular of Malaysia does not pose radiological hazard to the building dwellers. (author)

  8. Radiological-dose assessments of atolls in the northern Marshall Islands

    International Nuclear Information System (INIS)

    Robison, W.L.

    1983-04-01

    The Marshall Islands in the Equatorial Pacific, specifically Enewetak and Bikini Atolls, were the site of US nuclear testing from 1946 through 1958. In 1978, the Northern Marshall Islands Radiological Survey was conducted to evaluate the radiological conditions of two islands and ten atolls downwind of the proving grounds. The survey included aerial external gamma measurements and collection of soil, terrestrial, and marine samples for radionuclide analysis to determine the radiological dose from all exposure pathways. The methods and models used to estimate doses to a population in an environment where natural processes have acted on the source-term radionuclides for nearly 30 y, data bases developed for the models, and results of the radiological dose analyses are described

  9. Assessment of Patients Radiation Dose During Interventional Radiological Procedure in PPUKM

    International Nuclear Information System (INIS)

    Mohd Khalid Matori; Husaini Salleh; Muhammad Jamal Muhammad Isa

    2014-01-01

    Interventional Radiology (IR) is a relatively new subspecialty of radiology. It is subspecialty where minimally invasive procedures are performed under radiological guidance using X-ray. This procedure can deliver high radiation doses compared with other radiological method due to long screening time. Because of these it is important to determine radiation doses received by patients undergoing IR procedures. It is to ensure that the dose is within the range deemed to be saved. A total of 128 patients undergoing IR procedures in PPUKM between 2012 and 2013 were study retrospectively. Dose area product (DAP) meter were used to measure the integral dose for the whole procedures. Mean kerma-area products for abdomen, head, pelvis, and thorax were 243.1, 107.3, 39.05 and 45.7 Gycm 2 , respectively. This study may provide the useful information which can be use to establish baseline patient dose data for dose optimizing study and carried out a recommendation on effective method of patient dose reduction during IR procedures. A more detail results of this study are presented in this paper. (author)

  10. Preliminary assessment of radiological doses in alternative waste management systems without an MRS facility

    International Nuclear Information System (INIS)

    Schneider, K.J.; Pelto, P.J.; Daling, P.M.; Lavender, J.C.; Fecht, B.A.

    1986-06-01

    This report presents generic analyses of radiological dose impacts of nine hypothetical changes in the operation of a waste management system without a monitored retrievable storage (MRS) facility. The waste management activities examined in this study include those for handling commercial spent fuel at nuclear power reactors and at the surface facilities of a deep geologic repository, and the transportation of spent fuel by rail and truck between the reactors and the repository. In the reference study system, the radiological doses to the public and to the occupational workers are low, about 170 person-rem/1000 metric ton of uranium (MTU) handled with 70% of the fuel transported by rail and 30% by truck. The radiological doses to the public are almost entirely from transportation, whereas the doses to the occupational workers are highest at the reactors and the repository. Operating alternatives examined included using larger transportation casks, marshaling rail cars into multicar dedicated trains, consolidating spent fuel at the reactors, and wet or dry transfer options of spent fuel from dry storage casks. The largest contribution to radiological doses per unit of spent fuel for both the public and occupational workers would result from use of truck transportation casks, which are smaller than rail casks. Thus, reducing the number of shipments by increasing cask sizes and capacities (which also would reduce the number of casks to be handled at the terminals) would reduce the radiological doses in all cases. Consolidating spent fuel at the reactors would reduce the radiological doses to the public but would increase the doses to the occupational workers at the reactors

  11. A comparison of newborn stylized and tomographic models for dose assessment in paediatric radiology

    International Nuclear Information System (INIS)

    Staton, R J; Pazik, F D; Nipper, J C; Williams, J L; Bolch, W E

    2003-01-01

    Establishment of organ doses from diagnostic and interventional examinations is a key component to quantifying the radiation risks from medical exposures and for formulating corresponding dose-reduction strategies. Radiation transport models of human anatomy provide a convenient method for simulating radiological examinations. At present, two classes of models exist: stylized mathematical models and tomographic voxel models. In the present study, organ dose comparisons are made for projection radiographs of both a stylized and a tomographic model of the newborn patient. Sixteen separate radiographs were simulated for each model at x-ray technique factors typical of newborn examinations: chest, abdomen, thorax and head views in the AP, PA, left LAT and right LAT projection orientation. For AP and PA radiographs of the torso (chest, abdomen and thorax views), the effective dose assessed for the tomographic model exceeds that for the stylized model with per cent differences ranging from 19% (AP abdominal view) to 43% AP chest view. In contrast, the effective dose for the stylized model exceeds that for the tomographic model for all eight lateral views including those of the head, with per cent differences ranging from 9% (LLAT chest view) to 51% (RLAT thorax view). While organ positioning differences do exist between the models, a major factor contributing to differences in effective dose is the models' exterior trunk shape. In the tomographic model, a more elliptical shape is seen thus providing for less tissue shielding for internal organs in the AP and PA directions, with corresponding increased tissue shielding in the lateral directions. This observation is opposite of that seen in comparisons of stylized and tomographic models of the adult

  12. Prospective radiological dose assessment. Amersham plc (Amersham site) variation application December 1998

    International Nuclear Information System (INIS)

    Allott, R.

    2001-01-01

    Amersham plc (previously Nycomed-Amersham plc) submitted an application to the Environment Agency in December 1998 for a variation to their radioactive waste discharge authorisations granted under the Radioactive Substances Act 1993. The application requested a reduction in the discharge limits for certain radionuclides and no change for the remaining radionuclides. Amersham plc undertook a further review of their discharge requirements and submitted a new assessment for revised limits in January 2001. This report provides an assessment of the radiological implications of discharges at these revised limits requested by Amersham plc and the limits proposed by the Agency. It has been prepared by the National Compliance Assessment Service at the request of Thames Region to support their determination of the application. Four candidate critical groups were identified who could be exposed to discharges from the Amersham site: 1) Sewage workers at the Maple Lodge sewage works who might be exposed to external radiation from discharges contained within sewage and inadvertently inhale or ingest sewage. 2) Anglers on the Grand Union Canal who eat a small proportion of their annual catch of freshwater fish, who drink water abstracted solely from the River Colne and eat vegetables irrigated by water from the canal. 3) Persons living closest to site who eat locally produced food. 4) Dog walkers living near to site who eat locally produced food. For continuous discharges at the Agency's proposed annual limits, the highest dose of 160 μSv/y is predicted to be received by infants who live closest to the site and eat locally produced food. Therefore, this has been identified as the critical group. Children and adults living at the same location and eating locally produced food receive doses of 140 μSv/y and 130 μSv/y respectively. The critical group dose is less than the source constraint of 300 μSv/y. The dose is dominated by direct radiation from the site (110 μSv/y) and the

  13. Radiological dose assessments in the northern Marshall Islands (1989--1991)

    International Nuclear Information System (INIS)

    Sun, L.C.; Meinhold, C.B.; Moorthy, A.R.; Clinton, J.H.; Kaplan, E.

    1992-01-01

    The present Brookhaven National Laboratory (BNL) Marshall Islands Radiological Safety Program (MIRSP) began in 1987 with funding from the US Department of Energy (DOE). The objectives of the MIRSP are to determine the radionuclides present in the bodies of those people potentially exposed to residual radionuclide from weapon tests and fallout, and to assess their present and lifetime dose from external and internal sources. Field bioassay missions involving whole body counting (WBC) and urine sample collection have, therefore, been important components of the program. WBC is used to measure γ-emitters, such as 40 K, 60 Co and 137 Cs, present in individuals. Urine samples are used to measure α and β-emitting nuclides, such as 239 Pu and 90 Sr, that are undetectable by WBC routine methods

  14. Radiological dose assessments in the northern Marshall Islands (1989--1991)

    International Nuclear Information System (INIS)

    Sun, L.C.; Meinhold, C.B.; Moorthy, A.R.; Clinton, J.H.; Kaplan, E.

    1991-12-01

    The Republic of the Marshall Islands (RMI) is located in the central Pacific Ocean about 3500 km southeast of Hawaii and 4500 km east of Manila, Philippines. It consists of 34 atolls and 2 coral island, having a total land area of about 180 km 2 , distributed over more than 2.5 x 10 6 km 2 of ocean. Between 1946 and 1958 the United States conducted nuclear tests there: 43 at Enewetak and 23 at Bikini. Thirty-three years after the cessation of nuclear testing in the RMI, the impact of these operations on the health and radiological safety of the people living in or planing to return to their contaminated homelands is still an important concern. The present Brookhaven National Laboratory (BNL) Marshall Islands Radiological Safety Program (MIRSP) began in 1987 with funding from the US Department of Energy (DOE). The objectives of the MIRSP are to determine the radionuclides present in the bodies of those people potentially exposed to residual radionuclide from weapon tests and fallout, and to assess their present and lifetime dose from external and internal sources. Field bioassay missions involving whole-body counting (WBC) and urine sample collection have, therefore, been important components of the program. WBC is used to measure γ-emitters, such as 40 K, 60 Co and 137 Cs, present in individuals. Urine samples are used to measure α and β-emitting nuclides, such as 239 Pu and 90 Sr, that are undetectable by WBC routine methods. 6 refs

  15. Radiological dose assessments in the northern Marshall Islands (1989--1991)

    International Nuclear Information System (INIS)

    Sun, L.C.; Meinhold, C.B.; Moorthy, A.R.; Clinton, J.H.; Kaplan, E.

    1991-11-01

    The Republic of the Marshall Islands (RMI) is located in the central Pacific Ocean about 3500 km southwest of Hawaii and 4500 km east of Manila, Philippines. It consists of 34 atolls and 2 coral islands, having a total land area of about 180 km 2 , distributed over more than 2.5 x 10 6 of ocean. Between 1946 and 1958 the United states conducted nuclear tests there: 43 at Enewetak and 23 at Bikini. Thirty-three years after the cessation of nuclear testing in the RMI, the impact of these operations on the health and radiological safety of the people living in or planning to return to their contaminated homelands is still an important concern. The present Brookhaven National Laboratory (BNL) Marshall Islands Radiological Safety Program (MIRSP) began in 1987 with funding from the US Department of Energy (DOE). The objectives of the MIRSP are to determine the radionuclides present in the bodies of those people potentially exposed to residual radionuclide from weapon tests and fallout, and to assess their present and lifetime dose from external and internal sources. Field bioassay missions involving whole-body counting (WBC) and urine sample collection have, therefore, been important components of the program. WBC is used to measure γ-emitters, such as 40 K, 60 Co and 137 Cs, present in individuals. Urine samples are used to measure α and β-emitting nuclides such as 239 Pu and 90 Sr, that are undetectable by WBC routine methods

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

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  17. Radiation dose in dental radiology

    International Nuclear Information System (INIS)

    Cohnen, M.; Kemper, J.; Moedder, U.; Moebes, O.; Pawelzik, J.

    2002-01-01

    The aim of this study was to compare radiation exposure in panoramic radiography (PR), dental CT, and digital volume tomography (DVT). An anthropomorphic Alderson-Rando phantom and two anatomical head phantoms with thermoluminescent dosimeters fixed at appropriate locations were exposed as in a dental examination. In PR and DVT, standard parameters were used while variables in CT included mA, pitch, and rotation time. Image noise was assessed in dental CT and DVT. Radiation doses to the skin and internal organs within the primary beam and resulting from scatter radiation were measured and expressed as maximum doses in mGy. For PR, DVT, and CT, these maximum doses were 0.65, 4.2, and 23 mGy. In dose-reduced CT protocols, radiation doses ranged from 10.9 to 6.1 mGy. Effective doses calculated on this basis showed values below 0.1 mSv for PR, DVT, and dose-reduced CT. Image noise was similar in DVT and low-dose CT. As radiation exposure and image noise of DVT is similar to low-dose CT, this imaging technique cannot be recommended as a general alternative to replace PR in dental radiology. (orig.)

  18. Assessment of fetal radiation dose to patients and staff in diagnostic radiology

    International Nuclear Information System (INIS)

    Osei, E.K.

    2000-07-01

    A major source of uncertainty in the estimation of fetal absorbed radiation dose is the influence of fetal size and position as these change with gestational age. Consequently, dose to the fetus is related to gestational age. Most studies of fetal dose estimation during pregnancy assume that the uterus dose is equal to fetal dose. These dose estimates do not take account of gestational age and individual fetal depth, factors which are significant when calculating dose. To establish both positional and size data for estimation of fetal absorbed dose from radiological examinations, the depths from the mother's anterior surface to the mid-line of the fetal head and abdomen were measured from ultrasound scans in 215 pregnant women. Depths were measured along a ray path projected in the anterior-posterior direction from the mother's abdomen. The fetal size was estimated from measurements of the fetal abdominal and head circumference, femur length and the biparietal diameter. The effects of fetal presentation, maternal bladder volume, placenta location, gestational age and maternal AP thickness on fetal depth and size were analysed. A Monte Carlo (MC) model was developed, and used to derive factors for converting dose-area product and free-in-air entrance surface dose from medical exposure of a pregnant patient to absorbed dose to the uterus/embryo, and for converting uterus dose to fetal dose in the later stages of pregnancy. Also presented are factors for converting thermoluminescence dosimeter reading from occupational exposure of a pregnant worker to equivalent dose to the fetus. The MC model was verified experimentally by direct measurement of uterus depth dose in a female Rando phantom, and also by comparison with other experimental work and MC results in the literature. The application of the various conversion factors is demonstrated by a review of the dose estimation process in 50 cases of fetal irradiation from medical exposures. (author)

  19. Post-Remediation Radiological Dose Assessment, Linde Site, Tonawanda, New York

    Energy Technology Data Exchange (ETDEWEB)

    Kamboj, Sunita [Argonne National Lab. (ANL), Argonne, IL (United States); Durham, Lisa A. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2014-06-01

    A post-remediation radiological dose assessment was conducted for the Formerly Utilized Sites Remedial Action Program (FUSRAP) Linde Site by using the measured residual concentrations of the radionuclides of concern following the completion of the soils remedial action. The site’s FUSRAP-related contaminants of concern (COCs) are radionuclides associated with uranium processing activities conducted by the Manhattan Engineer District (MED) in support of the Nation’s early atomic energy and weapons program and include radium-226 (Ra-226), thorium-230 (Th-230), and total uranium (Utotal). Remedial actions to address Linde Site soils and structures were conducted in accordance with the Record of Decision for the Linde Site, Tonawanda, New York (ROD) (USACE 2000a). In the ROD, the U.S. Army Corps of Engineers (USACE) determined that the cleanup standards found in Title 40, Part 192 of the Code of Federal Regulations (40 CFR Part 192), the standards for cleanup of uranium mill sites designated under the Uranium Mill Tailings Radiation Control Act (UMTRCA), and the Nuclear Regulatory Commission (NRC) standards for decommissioning of licensed uranium and thorium mills, found in 10 CFR Part 40, Appendix A, Criterion 6(6), are Applicable or Relevant and Appropriate Requirements (ARARs) for cleanup of MED-related contamination at the Linde Site. The major elements of this remedy will involve excavation of the soils with COCs above soil cleanup levels and placement of clean materials to meet the other criteria of 40 CFR Part 192.

  20. Assessment of dose in thyroid and salivary glands in dental radiology using thermoluminescent dosimetry

    International Nuclear Information System (INIS)

    Mantuano, Natalia de O.; Silva, Ademir X. da; Correa, Samanda C.A.

    2011-01-01

    Radiobiological and epidemiological studies have provided evidence of risk of salivary and thyroid glands tumors incidence associated with oral radiology. Based on these studies, the tissue weighting factors were reviewed by the International Commission on Radiological Protection (ICRP) in 2007. The main objective of the present work is to estimate the absorbed dose on thyroid and salivary glands (parotid, submandibular and sublingual), during a complete periapical examination. The complete periapical examination was simulated using a Spectro 70X Seletronic X-ray dental equipment on an Alderson Rando phantom with Harshaw LiF:Mg,Ti thermoluminescent dosemeters (TLD100). A PTW DIADOS dosimetric system was used for calibration. The TLD100 were inserted into the phantom slices corresponding to the organs of interest. During a complete periapical examination, the highest evaluated mean absorbed dose was 4.9 mGy in the right submandibular gland and the lowest one of 1.5 mGy in the left thyroid lobe. Entrance surface doses ranged from 2.1 to 2.6 mGy, measured, respectively, for the techniques of upper left molar and lower right molar. When compared with the diagnostic reference levels (DRL), the entrance surface doses values were lower than the DRLs recommended in Brazilian current legislation. However, the dosimetric results show the need of optimization for complete periapical examination to minimize patient exposure. Measurements were performed without the use of thyroid protectors. The use of this device is certainly an easy and simple method of dose reduction. (author)

  1. Assessment of dose in thyroid and salivary glands in dental radiology using thermoluminescent dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    Mantuano, Natalia de O.; Silva, Ademir X. da [Instituto Alberto Luiz Coimbra de Pos-Graduacao e Pesquisa em Engenharia (PEN/COPPE/UFRJ), RJ (Brazil). Programa de Engenharia Nuclear; Canevaro, Luca V.; Mauricio, Claudia Lucia P. [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ) Rio de Janeiro, RJ (Brazil); Correa, Samanda C.A., E-mail: scorrea@cnen.gov.b [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)

    2011-07-01

    Radiobiological and epidemiological studies have provided evidence of risk of salivary and thyroid glands tumors incidence associated with oral radiology. Based on these studies, the tissue weighting factors were reviewed by the International Commission on Radiological Protection (ICRP) in 2007. The main objective of the present work is to estimate the absorbed dose on thyroid and salivary glands (parotid, submandibular and sublingual), during a complete periapical examination. The complete periapical examination was simulated using a Spectro 70X Seletronic X-ray dental equipment on an Alderson Rando phantom with Harshaw LiF:Mg,Ti thermoluminescent dosemeters (TLD100). A PTW DIADOS dosimetric system was used for calibration. The TLD100 were inserted into the phantom slices corresponding to the organs of interest. During a complete periapical examination, the highest evaluated mean absorbed dose was 4.9 mGy in the right submandibular gland and the lowest one of 1.5 mGy in the left thyroid lobe. Entrance surface doses ranged from 2.1 to 2.6 mGy, measured, respectively, for the techniques of upper left molar and lower right molar. When compared with the diagnostic reference levels (DRL), the entrance surface doses values were lower than the DRLs recommended in Brazilian current legislation. However, the dosimetric results show the need of optimization for complete periapical examination to minimize patient exposure. Measurements were performed without the use of thyroid protectors. The use of this device is certainly an easy and simple method of dose reduction. (author)

  2. Radiological environmental dose assessment methods and compliance dose results for 2015 operations at the Savannah River Site

    International Nuclear Information System (INIS)

    Jannik, G. T.; Dixon, K. L.

    2016-01-01

    This report presents the environmental dose assessment methods and the estimated potential doses to the offsite public from 2015 Savannah River Site (SRS) atmospheric and liquid radioactive releases. Also documented are potential doses from special-case exposure scenarios - such as the consumption of deer meat, fish, and goat milk.

  3. Radiological environmental dose assessment methods and compliance dose results for 2015 operations at the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Jannik, G. T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Dixon, K. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2016-09-01

    This report presents the environmental dose assessment methods and the estimated potential doses to the offsite public from 2015 Savannah River Site (SRS) atmospheric and liquid radioactive releases. Also documented are potential doses from special-case exposure scenarios - such as the consumption of deer meat, fish, and goat milk.

  4. Radiological hazards of Narghile (hookah, shisha, goza) smoking: activity concentrations and dose assessment

    Energy Technology Data Exchange (ETDEWEB)

    Khater, Ashraf E.M. [National Center for Nuclear Safety and Radiation Control, Atomic Energy Authority, Cairo (Egypt); Physics Department, College of Sciences, King Saud University, P.O. Box 2455, 11451 Riyadh (Saudi Arabia)], E-mail: khater_ashraf@yahoo.com; Abd El-Aziz, Nawal S. [National Center for Nuclear Safety and Radiation Control, Atomic Energy Authority, Cairo (Egypt); Al-Sewaidan, Hamed A. [Physics Department, College of Sciences, King Saud University, P.O. Box 2455, 11451 Riyadh (Saudi Arabia); Chaouachi, Kamal [DIU Tobaccology, University of Paris XI-XII (France)

    2008-12-15

    Narghile (hookah, shisha, goza, 'water-pipe') smoking has become fashionable worldwide. Its tobacco pastes, known as moassel and jurak, are not standardized and generally contain about 30-50% (sometimes more) tobacco, molasses/juice of sugarcane, various spices and dried fruits (particularly in jurak) and, in the case of moassel, glycerol and flavoring essences. Tobacco contains minute amounts of radiotoxic elements such as {sup 210}Pb, {sup 210}Po and uranium, which are inhaled via smoking. Only very few data have been published on the concentrations of natural radionuclides in narghile tobacco mixtures. Consequently, the aim of this study was to draw first conclusions on the potential hazards of radioactivity in moassel tobacco in relation to narghile smoking. The results indicate the existence of a wide range in the radioactivity contents where the average (range) activity concentrations of {sup 238}U, {sup 234}Th {sup 226}Ra, {sup 210}Pb, {sup 210}Po, {sup 232}Th and {sup 40}K, in Bq/kg dry weight were 55 (19-93), 11 (3-23), 3 (1.2-8), 14 (3-29), 13 (7-32), 7 (4-10) and 719 (437-1044) Bq/kg dry weight, respectively. The average concentrations of natural radionuclides in moassel tobacco pastes are comparable to their concentration in Greek cigarettes and tobacco leaves, and lower than that of Brazilian tobacco leaves. The distribution pattern of these radionuclides after smoking, between smoke, ash and filter, is unknown, except for {sup 210}Po during cigarette smoking and from one existing study during moassel smoking. Radiological dose assessment due to intake of natural radionuclides was calculated and the possible radio-toxicity of the measured radionuclides is briefly discussed.

  5. Assessment of eye lens doses in interventional radiology: a simulation in laboratory conditions

    International Nuclear Information System (INIS)

    Cemusova, Z.; Ekendahl, D.; Judas, L.

    2016-01-01

    As workers in interventional radiology belong to one of the most occupationally exposed groups, methods for sufficiently accurate quantification of their external exposure are sought. The objective of the authors' experiment was to investigate the relations between eye lens dose and H p (10), H p (3) or H p (0.07) values measured with a conventional whole-body personal thermoluminescence dosemeter (TLD). Conditions of occupational exposure during common interventional procedures were simulated in laboratory. An anthropomorphic phantom represented a physician. The TLDs were fixed to the phantom in different locations that are common for purposes of personal dosimetry. In order to monitor the dose at the eye lens level during the exposures, a special thermoluminescence eye dosemeter was fixed to the phantom's temple. Correlations between doses measured with the whole-body and the eye dosemeters were found. There are indications that personnel in interventional radiology do not need to be unconditionally equipped with additional eye dosemeters, especially if an appropriate whole-body dosimetry system has been already put into practice. (authors)

  6. Dose from radiological examinations

    International Nuclear Information System (INIS)

    Imamura, Keiko; Uji, Teruyuki; Sakuyama, Keiko; Fujikawa, Mitsuhiro; Fujii, Masamichi

    1976-01-01

    Relatively high gonad doses, several hundred to one thousand mR, have been observed in case of pelvis, hip-joint, coccyx, lower abdomen and lumber examination. Dose to the ovary is especially high in barium enema and I.V.P. examinations. About 12 per cent of the 4-ray examination are high-dose. The gonad dose is relatively high in examination of abdomen and lower extremities, in infants. The dose to the eyes is especially high, 1.0 to 2.5R per exposure, in temporal bone and nasal sinuses tomography. X-ray doses have been compared with dose limits recommended by ICRP and with the gonad dose from natural radiations. The gonad dose in lumbar examination, barium enema, I.V.P. etc. is as high as the maximum permissible dose per year recommended by ICRP. Several devices have been made for dose reduction in the daily examinations: (1) separating the radiation field from the gonad by one centimeter decreases the gonad dose about one-half. (2) using sensitive screens and films. In pelvimetry and in infant hip-joint examination, the most sensitive screen and film are used. In the I.V.P. examination of adult, use of MS screen in place of FS screen decreases the dose to one-third, in combination with careful setting of radiation field, (3) use of grid increases the dose about 50 percent and the lead rubber protection (0.1mm lead equivalent) decreases the gonad dose to one-thirtieth in the spinal column examination of infant, (4) A lead protector, 1mm thickness and 2.5cm in diameter, on the eyes decreases the dose to about one-eighth in the face and nead examinations. These simple and effective methods for dose reduction. Should be carried out in as many examinations as possible in addition to observing dose limits recommended by ICRP. (Evans, J.)

  7. Development of double dosimetry algorithm for assessment of effective dose to staff in interventional radiology

    International Nuclear Information System (INIS)

    Kim, Ji Young

    2011-02-01

    Medical staff involving interventional radiology(IR) procedures are significantly exposed to the scatter radiation because they stand in close proximity to the patient. Since modern IR techniques are often very complicated and require extended operation time, doses to IR workers tend to increase considerably. In general, the personal dose equivalent at 10 mm depth, H p (10), read from one dosimeter worn on the trunk of a radiation worker is assumed to be a good estimate of the effective dose and compared to the dose limits for regulatory compliance. This assumption is based on the exposure conditions that the radiation field is broad and rather homogeneous. However, IR workers usually wear protective clothing like lead aprons and thyroid shield which allow part of the body being exposed to much higher doses. To solve this problem, i.e. to adequately estimate the effective doses of IR workers, use of double dosimeters, one under the apron and one over the apron where unshielded part of the body exposed, was recommended. Several algorithms on the interpretation of the two dosimeter readings have been proposed. However, the dosimeter weighting factors applied to the algorithm differ significantly, which quests a question on the reliability of the algorithm. Moreover, there are some changes in the process of calculating the effective dose in the 2007 recommendations of the International Commission on Radiological Protection(ICRP): changes in the radiation weighting factors, tissue weighting factors and the computational reference phantoms. Therefore, this study attempts to set a new algorithm for interpreting two dosimeter readings to provide a proper estimate of the effective dose for IR workers, incorporating those changes in definition of effective dose. The effective doses were estimated using Monte Carlo simulations for various practical conditions based on the vogel reference phantom and the new tissue weighting factors. A quasi-effective dose, which is

  8. Development of double dosimetry algorithm for assessment of effective dose to staff in interventional radiology

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ji Young

    2011-02-15

    Medical staff involving interventional radiology(IR) procedures are significantly exposed to the scatter radiation because they stand in close proximity to the patient. Since modern IR techniques are often very complicated and require extended operation time, doses to IR workers tend to increase considerably. In general, the personal dose equivalent at 10 mm depth, H{sub p}(10), read from one dosimeter worn on the trunk of a radiation worker is assumed to be a good estimate of the effective dose and compared to the dose limits for regulatory compliance. This assumption is based on the exposure conditions that the radiation field is broad and rather homogeneous. However, IR workers usually wear protective clothing like lead aprons and thyroid shield which allow part of the body being exposed to much higher doses. To solve this problem, i.e. to adequately estimate the effective doses of IR workers, use of double dosimeters, one under the apron and one over the apron where unshielded part of the body exposed, was recommended. Several algorithms on the interpretation of the two dosimeter readings have been proposed. However, the dosimeter weighting factors applied to the algorithm differ significantly, which quests a question on the reliability of the algorithm. Moreover, there are some changes in the process of calculating the effective dose in the 2007 recommendations of the International Commission on Radiological Protection(ICRP): changes in the radiation weighting factors, tissue weighting factors and the computational reference phantoms. Therefore, this study attempts to set a new algorithm for interpreting two dosimeter readings to provide a proper estimate of the effective dose for IR workers, incorporating those changes in definition of effective dose. The effective doses were estimated using Monte Carlo simulations for various practical conditions based on the vogel reference phantom and the new tissue weighting factors. A quasi-effective dose, which is

  9. Assessment of medical radiation exposure to patients and ambient doses in several diagnostic radiology departments

    Science.gov (United States)

    Sulieman, A.; Elhadi, T.; Babikir, E.; Alkhorayef, M.; Alnaaimi, M.; Alduaij, M.; Bradley, D. A.

    2017-11-01

    In many countries diagnostic medical exposures typically account for a very large fraction of the collective effective dose that can be assigned to anthropological sources and activities. This in part flags up the question of whether sufficient steps are being taken in regard to potential dose saving from such medical services. As a first step, one needs to survey doses to compare against those of best practice. The present study has sought evaluation of the radiation protection status and patient doses for certain key radiological procedures in four film-based radiology departments within Sudan. The radiation exposure survey, carried out using a survey meter and quality control test tools, involved a total of 299 patients their examinations being carried out at one or other of these four departments. The entrance surface air kerma (ESAK) was determined from exposure settings using DosCal software and an Unfors -Xi-meter. The mean ESAK for x-ray examination of the chest was 0.30±0.1 mGy, for the skull it was 0.96±0.7 mGy, for the abdomen 0.85±0.01 mGy, for spinal procedures 1.30±0.6 mGy and for procedures involving the limbs it was 0.43±0.3 mGy. Ambient dose-rates in the reception area, at the closed door of the x-ray room, recorded instantaneous values of up to 100 μSv/h. In regard to protection, the associated levels were found to be acceptable in three of the four departments, corrective action being required for one department, regular quality control also being recommended.

  10. A study on the food consumption rates for off-site radiological dose assessment around Korean Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lee, Gab Bock; Chung, Yang Geun

    2008-01-01

    The internal dose by food consumption mostly accounts for radiological dose of public around Nuclear Power Plants (NPPs). But, food consumption rates applied to off-site dose calculation in Korea which are the result of field investigation around Kori NPP by the KAERI (Korea Atomic Energy Research Institute) in 1988, are not able to reflect the latest dietary characteristics of Korean. The food consumption rates to be used for radiological dose assessment in Korea are based on the maximum individual of US NRC (Nuclear Regulatory Commission) Regulatory Guide 1.109. However, the representative individual of the critical group is considered in the recent ICRP (International Commission on Radiological Protection) recommendation and European nations' practice. Therefore, the study on the re-establishment of the food consumption rates for individual around nuclear power plant sites in Korea was carried out to reflect on the recent change of the Korean dietary characteristics and to apply the representative individual of critical group to domestic regulations. The ministry of Health and Welfare Affairs has investigated the food and nutrition of nations every 3 years based on the Law of National Health Improvement. The statistical data such as mean, standard deviation, various percentile values about food consumption rates to be used for the representative individual of the critical group were analyzed by using the raw data of the national food consumption survey in 2001∼2002. Also, the food consumption rates for maximum individual are re-estimated

  11. Calculating the radiological parameters used in non-human biota dose assessment tools using ERICA Tool and site-specific data

    Energy Technology Data Exchange (ETDEWEB)

    Sotiropoulou, Maria [INRASTES, NCSR ' ' Demokritos' ' , Environmental Radioactivity Laboratory, Athens (Greece); Aristotle University of Thessaloniki, Atomic and Nuclear Physics Laboratory, Thessaloniki (Greece); Florou, Heleny [INRASTES, NCSR ' ' Demokritos' ' , Environmental Radioactivity Laboratory, Athens (Greece); Kitis, Georgios [Aristotle University of Thessaloniki, Atomic and Nuclear Physics Laboratory, Thessaloniki (Greece)

    2017-11-15

    The substantial complexity in ecosystem-radionuclide interactions is difficult to be represented in terms of radiological doses. Thus, radiological dose assessment tools use typical exposure situations for generalized organisms and ecosystems. In the present study, site-specific data and radioactivity measurements of terrestrial organisms (grass and herbivore mammals) and abiotic components (soil) are provided. The retrieved data are used in combination with the ERICA Assessment Tool for calculation of radiological parameters. The process of radionuclide transfer within ecosystem components is represented using concentration ratios (CRs), while for the calculation of dose rates the dose conversion coefficient (DCC) methodology is applied. Comparative assessments are performed between the generic and assessment-specific radiological parameters and between the resulting dose rates. Significant differences were observed between CRs calculated in this study and those reported in the literature for cesium and thorium, which can easily be explained. On the other hand, CRs calculated for radium are in very good agreement with those reported in the literature. The DCCs exhibited some small differences between the reference and the assessment-specific organism due to mass differences. The differences were observed for internal and external dose rates, but they were less pronounced for total dose rates which are typically used in the assessment of radiological impact. The results of the current work can serve as a basis for further studies of the radiological parameters in environments that have not been studied yet. (orig.)

  12. Assessment of knowledge and awareness among radiology personnel regarding current computed tomography technology and radiation dose

    Science.gov (United States)

    Karim, M. K. A.; Hashim, S.; Bradley, D. A.; Bahruddin, N. A.; Ang, W. C.; Salehhon, N.

    2016-03-01

    In this paper, we evaluate the level of knowledge and awareness among 120 radiology personnel working in 7 public hospitals in Johor, Malaysia, concerning Computed Tomography (CT) technology and radiation doses based on a set of questionnaires. Subjects were divided into two groups (Medical profession (Med, n=32) and Allied health profession (AH, n=88). The questionnaires are addressed: (1) demographic data (2) relative radiation dose and (3) knowledge of current CT technology. One-third of respondents from both groups were able to estimate relative radiation dose for routine CT examinations. 68% of the allied health profession personnel knew of the Malaysia regulations entitled ‘Basic Safety Standard (BSS) 2010’, although notably 80% of them had previously attended a radiation protection course. No significant difference (p < 0.05) in mean scores of CT technology knowledge detected between the two groups, with the medical professions producing a mean score of (26.7 ± 2.7) and the allied health professions a mean score of (25.2 ± 4.3). This study points to considerable variation among the respondents concerning their understanding of knowledge and awareness of risks of radiation and CT optimization techniques.

  13. Assessment of knowledge and awareness among radiology personnel regarding current computed tomography technology and radiation dose

    International Nuclear Information System (INIS)

    Karim, M K A; Hashim, S; Bahruddin, N A; Ang, W C; Salehhon, N; Bradley, D A

    2016-01-01

    In this paper, we evaluate the level of knowledge and awareness among 120 radiology personnel working in 7 public hospitals in Johor, Malaysia, concerning Computed Tomography (CT) technology and radiation doses based on a set of questionnaires. Subjects were divided into two groups (Medical profession (Med, n=32) and Allied health profession (AH, n=88). The questionnaires are addressed: (1) demographic data (2) relative radiation dose and (3) knowledge of current CT technology. One-third of respondents from both groups were able to estimate relative radiation dose for routine CT examinations. 68% of the allied health profession personnel knew of the Malaysia regulations entitled ‘Basic Safety Standard (BSS) 2010’, although notably 80% of them had previously attended a radiation protection course. No significant difference (p < 0.05) in mean scores of CT technology knowledge detected between the two groups, with the medical professions producing a mean score of (26.7 ± 2.7) and the allied health professions a mean score of (25.2 ± 4.3). This study points to considerable variation among the respondents concerning their understanding of knowledge and awareness of risks of radiation and CT optimization techniques. (paper)

  14. Conventional radiology and genetic dose

    International Nuclear Information System (INIS)

    Gonzalez-Vila, V.; Fernandez, A.; Rivera, F.; Martinez, M.; Gomez, A.; Luis, J.

    1992-01-01

    A research project was established in 1984 to evaluate the expected genetic abnormalities due to radiation received by the population attending the Outpatient Radiological Service due to medical radiological practices. The study was conducted in 1985 (12 weeks chosen by random). The equivalent gonadal dose was the chosen parameter, representing the social cost of the radiology. Samples of 2945 men and 2929 women were considered in the study. The number of genetic abnormalities, in relation to the mean age of reproduction (a generation every 30 years), was 2.13 cases per million in the first generation and 15.97 cases per million at equilibrium. The authors interpretation is that both the method and the expected genetic detriment are suitable procedures for the characterisation of the Radiological Service as a radiation source. (author)

  15. Patient dose assessment in various Interventional radiology and cardiology procedures in Algeria (IAEA regional project results)

    International Nuclear Information System (INIS)

    Khelassi-Toutaoui, Nadia; Merad, Ahmed; Toutaoui, A.E.K.; Bairi, Souad

    2008-01-01

    Full text: Purpose: To evaluate patient doses in Interventional Radiology (IR) and Cardiology (IC) procedures in Algeria, within the framework of an International Atomic Energy Agency (IAEA) regional project on radiation protection of patients and medical exposure control (RAF 9033). Materials and Methods: Three public hospitals (CHU Bab el Oued, CHU Parnet and CHU Mustapha) and one specialised Cardiology Service (Clinique Maouche) were chosen for the study. For Maximum Skin Dose (MSD) evaluation, gafchromic films XR type R were used, placed on patient's back before the procedure. The Dose Area Product (DAP) and MSD were measured in 57 IR and IC procedures, either diagnostic or therapeutic. Results: The results revealed large variations in MSD (0.06-3.3 Gy) and DAP (5.5-332 mGycm 2 ). Mean MSD was 0.227 Gy in cerebral angiography, 0.202 Gy in coronary angiography, 1.162 Gy in Percutaneus Transluminal Coronary Angioplasty (PTCA) and 0.128 in abdominal angiography. The correlation of DAP and MSD was significant (r = 0.7). The correlation was DAP and fluoroscopy time was also significant (r = 0.8). Conclusion: The highest MSD values were found in PTCA which is a therapeutic procedure. Two PTCAs out of the 57 procedures measured in total had MSD over the threshold of 2 Gy for deterministic effects (MSD 1 = 3.0 Gy and MSD 2 3.3 Gy). The large variations in MSD reveal the need to continuously monitor patient doses in IR and IC procedures with special emphasis in PTCA procedure. (author)

  16. Updated radiological dose assessment of Bikini and Eneu Islands at Bikini Atoll

    International Nuclear Information System (INIS)

    Robison, W.L.; Mount, M.E.; Phillips, W.A.; Stuart, M.L.; Thompson, S.E.; Conrado, C.L.; Stoker, A.C.

    1982-01-01

    This report is part of a continuing effort to refine dose assessments for resettlement options at Bikini Atoll. Radionuclide concentration data developed at Bikini Atoll since 1977 have been used in conjunction with recent dietary information and current dose models to develop the annual dose rate and 30- and 50-y integral doses presented here for Bikini and Eneu Island living patterns. The terrestrial food chain is the most significant exposure pathway--it contributes more than 50% of the total dose--and external gamma exposure is the second most significant pathway. Other pathways evaluated are the marine food chain, drinking water, and inhalation. Cesium-137 produces more than 85% of the predicted dose; 90 Sr is the second most significant radionuclide; 60 Co contributes to the external gamma exposure in varying degrees, but is a small part of the total predicted dose; the transuranic radionuclides contribute a small portion of the total predicted lung and bone doses but do present a long-term source of exposure. Maximum annual dose rates for Bikini Island are about 1 rem/y for the whole body and bone marrow when imported foods are available and about 1.9 rem/y when imports are unavailable. Maximum annual dose rates for Eneu Island when imports are available are 130 mrem/y for the whole body and 136 mrem/y for bone marrow. Similar doses when imported foods are unavailable are 245 and 263 mrem/y, respectively. The 30-y integral doses for Bikini Island are about 23 rem for whole body and bone marrow when imported foods are available and more than 40 rem when imports are unavailable. The Eneu Island 30-y integral doses for whole body and bone marrow are about 3 rem when imports are available and 5.5 and 6.1 rem, respectively, when imports are unavailable. Doses from living patterns involving some combination of Bikini and Eneu Islands fall between the doses listed above for each island separately

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

    International Nuclear Information System (INIS)

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

    1996-01-01

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

  18. Technical basis for radiological release of Grand Junction Office Building 2. Volume 1, dose assessment

    International Nuclear Information System (INIS)

    Morris, R.; Warga, J.; Thorne, D.

    1997-07-01

    Building 2 on the US Department of Energy (DOE) Grand Junction Office (GJO) site is part of the GJO Remedial Action Program (GJORAP). During evaluation of Building 2 for determination of radiological release disposition, some inaccessible surface contamination measurements were detected to be greater than the generic surface contamination guidelines of DOE Order 5400.5 (which are functionally equivalent to US Nuclear Regulatory Commission [NRC] Regulatory Guide 1.86). Although the building is nominal in size, it houses the site telecommunications system, that is critical to continued GJO operations, and demolition is estimated at $1.9 million. Because unrestricted release under generic surface contamination guidelines is cost-prohibitive, supplemental standards consistent with DOE Order 5400.5 are being pursued. This report describes measurements and dose analysis modeling efforts to evaluate the radiation dose to members of the public who might occupy or demolish Building 2, a 2,480 square-foot (ft) building constructed in 1944. The north portion of the building was used as a shower facility for Manhattan Project uranium-processing mill workers and the south portion was a warehouse. Many originally exposed surfaces are no longer accessible for contamination surveys because expensive telecommunications equipment have been installed on the floors and mounted on panels covering the walls. These inaccessible surfaces are contaminated above generic contamination limits

  19. Validation of a mathematical phantom for dose assessment of radiological accidents

    International Nuclear Information System (INIS)

    Gomes, Joana D' Arc R.L.; Gomes, Rogerio S.; Costa, Mara Lucia L.

    2013-01-01

    Sealed radioactive sources are widely used in the industry with the purpose of well logging, non-destructive testing, food irradiation, process control systems, elemental analysis and others. Among the most used sources, it can mention: 137 Cs, 60 Co, 192 Ir, 85 Kr and Americium-Beryllium with radiation activities ranging between a few MegaBecquerels (MBq) to million of GBq, as the case of food irradiation. In general, these sources present sufficient activity to represent a significant health hazard when inadequately shielded or not handled according to proper safety procedures, producing radiation exposures to workers and to members of public. In cases of overexposure to ionizing radiation, an estimative of the dose received by victims of radiation accidents, as well as its distribution within the organism, can be provided by use an anthropomorphic phantom associates with a theoretical simulation Monte Carlo method to simulate the radioactive source and its interactions with the phantom. In this work is presented the validation results of application of a mathematical phantom modeled in Geant4, as a tool to reconstruct dose of radiological accidents due to external exposure. The results are compared with the dosimetry of real accidents. (author)

  20. Assessment of the radiological impact of gamma and radon dose rates at former U mining sites in Tajikistan

    International Nuclear Information System (INIS)

    Lespukh, E.; Stegnar, P.; Yunusov, M.; Tilloboev, H.; Zyazev, G.; Kayukov, P.; Hosseini, A.; Strømman, G.; Salbu, B.

    2013-01-01

    An assessment of the radiological situation due to exposure to gamma radiation, radon ( 222 Rn) and thoron ( 220 Rn) was carried out at former uranium (U) mining and processing sites in Taboshar and at Digmai in Tajikistan. Gamma dose rate measurements were made using various field instruments. 222 Rn/ 220 Rn measurements were carried out with field instruments for instantaneous measurements and then discriminative 222 Rn/ 220 Rn solid state nuclear track detectors (SSNTD) were used for longer representative measurements. The detectors were exposed for an extended period of time in different outdoor and indoor public and residential environments at the selected U legacy sites. The results showed that gamma, 222 Rn and 220 Rn doses were in general low, which consequently implies a low to relatively low radiological risk. The radiation doses deriving from external radiation (gamma dose rate), indoor 222 Rn and 220 Rn with their short-lived progenies did not exceed national or international standards. At none of the sites investigated did the average individual annual effective doses exceed 10 mSv, the recommended threshold value for the general public. A radiation hazard could be associated with exceptional situations, such as elevated exposures to ionizing radiation at the Digmai tailings site and/or in industrial facilities, where gamma and 222 Rn/ 220 Rn dose rates could reach values of several 10 mSv/a. Current doses of ionizing radiation do not represent a hazard to the health of the resident public, with the exception of some specific situations. These issues should be adequately addressed to further reduce needless exposure of the resident public to ionizing radiation

  1. Dose assessment in environmental radiological protection: State of the art and perspectives.

    Science.gov (United States)

    Stark, Karolina; Goméz-Ros, José M; Vives I Batlle, Jordi; Lindbo Hansen, Elisabeth; Beaugelin-Seiller, Karine; Kapustka, Lawrence A; Wood, Michael D; Bradshaw, Clare; Real, Almudena; McGuire, Corynne; Hinton, Thomas G

    2017-09-01

    Exposure to radiation is a potential hazard to humans and the environment. The Fukushima accident reminded the world of the importance of a reliable risk management system that incorporates the dose received from radiation exposures. The dose to humans from exposure to radiation can be quantified using a well-defined system; its environmental equivalent, however, is still in a developmental state. Additionally, the results of several papers published over the last decade have been criticized because of poor dosimetry. Therefore, a workshop on environmental dosimetry was organized by the STAR (Strategy for Allied Radioecology) Network of Excellence to review the state of the art in environmental dosimetry and prioritize areas of methodological and guidance development. Herein, we report the key findings from that international workshop, summarise parameters that affect the dose animals and plants receive when exposed to radiation, and identify further research needs. Current dosimetry practices for determining environmental protection are based on simple screening dose assessments using knowledge of fundamental radiation physics, source-target geometry relationships, the influence of organism shape and size, and knowledge of how radionuclide distributions in the body and in the soil profile alter dose. In screening model calculations that estimate whole-body dose to biota the shapes of organisms are simply represented as ellipsoids, while recently developed complex voxel phantom models allow organ-specific dose estimates. We identified several research and guidance development priorities for dosimetry. For external exposures, the uncertainty in dose estimates due to spatially heterogeneous distributions of radionuclide contamination is currently being evaluated. Guidance is needed on the level of dosimetry that is required when screening benchmarks are exceeded and how to report exposure in dose-effect studies, including quantification of uncertainties. Further

  2. A study on the radiation and environmental safety -Development of a real-time radiological dose assessment system-

    Energy Technology Data Exchange (ETDEWEB)

    Han, Moon Heui; Lee, Yung Bok; Kim, Eun Han; Suh, Kyung Suk; Hwang, Won Tae [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    The real-time dose assessment system under development has been updated and the technology for tracer experiment has been established. The calculation of external gamma dose is the most difficult and time-consuming part of the dose calculations. The characteristics of external gamma exposure have been investigated and the method for reducing the calculation time has been devised. The internal exposure via the ingestion of the contaminated foodstuffs is one of the important pathways to the total radiological exposure. In the emergency, it is necessary to take an action such like food ban to protect the internal exposure. An algorithm for the interface between the real-time system and the food chain model has been provided. The second field tracer experiment over flat terrain has been carried out on a plain in Iksan city in Junrabook-Do. Sequential tracer sampler which can be sampled the tracer gas over arbitrary 12 time interval has been designed and manufactured. SF{sub 6} has been used as the tracer gas and the sampled gas has been analysed by gas-chromatographer. 55 figs, 32 tabs, 65 refs. (Author).

  3. EcoDoses improving radiological assessment of doses to man from terrestrial ecosystems. A status report for the NKS-B project 2003

    Energy Technology Data Exchange (ETDEWEB)

    Bergan, T. [Lavrans Skuterud, Haevard Thoerring (Norway); Liland, A. [Norwegian Radiation Protection Authority (NRPA) (Denmark)] (eds.)

    2004-05-01

    The NKS B-programme EcoDoses project started in 2003 as a collaboration between all the Nordic countries. The aim of the project is to improve the radiological assessments of doses to man from terrestrial ecosystems. The first part, conducted in 2003, has focussed on an extensive collation and review of both published and unpublished data from all the Nordic countries for the nuclear weapons fallout period and the post-Chemobyl period. This included data on radionuclides in air filters, precipitation, soil samples, milk and reindeer. Based on this, an improved model for estimating radioactive fallout based on precipitation data during the nuclear weapons fallout period has been developed. Effective ecological half- lives for 137Cs and 90Sr in milk have been calculated for the nuclear weapons fallout period. For reindeer the ecological half- lives for 137Cs have been calculated for both the nuclear weapons fallout period and the post-Chemobyl period. The data were also used to compare modelling results with observed concentrations. This was done at a workshop where the radioecological food-and-dose module in the ARGOS decision support system was used to predict transfer of deposited radionuclides to foodstuffs and subsequent radiation doses to man. The work conducted the first year is presented in this report and gives interesting, new results relevant for terrestrial radioecology. (au)

  4. EcoDoses. Improving radiological assessment of doses to man from terrestrial ecosystems. A status report for the NKS-B project 2004

    Energy Technology Data Exchange (ETDEWEB)

    Nielsen, Sven P.; Isaksson, M.; Nilsson, Elisabeth (and others)

    2005-07-01

    The NKS B-programme EcoDoses project started in 2003 as a collaboration between all the Nordic countries. The aim of the project is to improve the radiological assessments of doses to man from terrestrial ecosystems. The present report sums up the work performed in the second phase of the project. The main topics in 2004 have been: (i) A continuation of previous work with a better approach for estimating global fallout on a regional or national scale, based on a correlation between precipitation and deposition rates. (ii) Fur-ther extension of the EcoDoses milk database. Estimation of effective ecological half lives of {sup 137}Cs in cows milk focussing on suitable post-Chernobyl time-series. Modelling integrated transfer of {sup 13}7{sup C}s to cow's milk from Nordic countries. (iii) Determination of effective ecological half lives for fresh water fish from Nordic lakes. (iv) Investigate ra-dioecological sensitivity for Nordic populations. (v) Food-chain modelling using the Eco-sys-model, which is the underlying food- and dose-module in several computerised deci-sion-making systems. (au)

  5. EcoDoses. Improving radiological assessment of doses to man from terrestrial ecosystems. A status report for the NKS-B project 2004

    International Nuclear Information System (INIS)

    Nielsen, Sven P.; Isaksson, M.; Nilsson, Elisabeth

    2005-07-01

    The NKS B-programme EcoDoses project started in 2003 as a collaboration between all the Nordic countries. The aim of the project is to improve the radiological assessments of doses to man from terrestrial ecosystems. The present report sums up the work performed in the second phase of the project. The main topics in 2004 have been: (i) A continuation of previous work with a better approach for estimating global fallout on a regional or national scale, based on a correlation between precipitation and deposition rates. (ii) Fur-ther extension of the EcoDoses milk database. Estimation of effective ecological half lives of 137 Cs in cows milk focussing on suitable post-Chernobyl time-series. Modelling integrated transfer of 13 7 C s to cow's milk from Nordic countries. (iii) Determination of effective ecological half lives for fresh water fish from Nordic lakes. (iv) Investigate ra-dioecological sensitivity for Nordic populations. (v) Food-chain modelling using the Eco-sys-model, which is the underlying food- and dose-module in several computerised deci-sion-making systems. (au)

  6. Radiological dose assessments in the Northern Marshall Islands (1989-1991)

    Energy Technology Data Exchange (ETDEWEB)

    Sun, L.C.; Meinhold, C.B.; Moorthy, A.R.; Clinton, J.H.; Kaplan, E. [Brookhaven National Laboratory, Radiological Science Div., Dept. of Nuclear Energy, Upton, New York (United States)

    1992-07-01

    The Republic of the Marshall Islands (RMI) is located in the central Pacific Ocean about 3,500 km southwest of Hawaii and 4,500 km east of Manila, Philippines. It consists of 34 atolls and 2 coral islands, having a total land area of about 180 km{sup 2} distributed over more then 2.5 x 10{sup 6} km{sup 2} of ocean. Between 1946 and 1958 the United States conducted nuclear tests there: 43 at Enewetak and 23 at Bikini. Thirty-three years after the cessation of nuclear testing in the RMI, the impact of these operations on the health and radiological safety of the people living in or planning to return to their contaminated homelands is still an important concern. (author)

  7. Radiological dose assessments in the Northern Marshall Islands (1989-1991)

    International Nuclear Information System (INIS)

    Sun, L.C.; Meinhold, C.B.; Moorthy, A.R.; Clinton, J.H.; Kaplan, E.

    1992-01-01

    The Republic of the Marshall Islands (RMI) is located in the central Pacific Ocean about 3,500 km southwest of Hawaii and 4,500 km east of Manila, Philippines. It consists of 34 atolls and 2 coral islands, having a total land area of about 180 km 2 distributed over more then 2.5 x 10 6 km 2 of ocean. Between 1946 and 1958 the United States conducted nuclear tests there: 43 at Enewetak and 23 at Bikini. Thirty-three years after the cessation of nuclear testing in the RMI, the impact of these operations on the health and radiological safety of the people living in or planning to return to their contaminated homelands is still an important concern. (author)

  8. Radiological assessment and optimization

    International Nuclear Information System (INIS)

    Zeevaert, T.; Sohier, A.

    1998-01-01

    The objectives of SCK-CEN's research in the field of radiological assessment and optimization are (1) to implement ALARA principles in activities with radiological consequences; (2) to develop methodologies for radiological optimization in decision-aiding; (3) to improve methods to assess in real time the radiological hazards in the environment in case of an accident; (4) to develop methods and programmes to assist decision-makers during a nuclear emergency; (5) to support the policy of radioactive waste management authorities in the field of radiation protection; (6) to investigate computer codes in the area of multi criteria analysis; (7) to organise courses on off-site emergency response to nuclear accidents. Main achievements in these areas for 1997 are summarised

  9. Assessment of radiological parameters and patient dose audit using semi-empirical model

    International Nuclear Information System (INIS)

    Olowookere, C.J.; Onabiyi, B.; Ajumobi, S. A.; Obed, R.I.; Babalola, I. A.; Bamidele, L.

    2011-01-01

    Risk is associated with all human activities, medical imaging is no exception. The risk in medical imaging is quantified using effective dose. However, measurement of effective dose is rather difficult and time consuming, therefore, energy imparted and entrance surface dose are obtained and converted into effective dose using the appropriate conversion factors. In this study, data on exposure parameters and patient characteristics were obtained during the routine diagnostic examinations for four common types of X-ray procedures. A semi-empirical model involving computer software Xcomp5 was used to determine energy imparted per unit exposure-area product, entrance skin exposure(ESE) and incident air kerma which are radiation dose indices. The value of energy imparted per unit exposure-area product ranges between 0.60 and 1.21x 10 -3 JR -1 cm -2 and entrance skin exposure range from 5.07±1.25 to 36.62±27.79 mR, while the incident air kerma range between 43.93μGy and 265.5μGy. The filtrations of two of the three machines investigated were lower than the standard requirement of CEC for the machines used in conventional radiography. The values of and ESE obtained in the study were relatively lower compared to the published data, indicating that patients irradiated during the routine examinations in this study are at lower health risk. The energy imparted per unit exposure- area product could be used to determine the energy delivered to the patient during diagnostic examinations, and it is an approximate indicator of patient risk.

  10. Biodosimetry versus physical dosimetry for emergency dose assessment following large-scale radiological exposures

    International Nuclear Information System (INIS)

    McKeever, S.W.S.; Sholom, S.

    2016-01-01

    Existing data on intercomparisons involving biodosimetry or physical dosimetry methods are analyzed and the results interpreted regarding their efficacy in triage in emergency dosimetry following mass casualty radiological events. The biodosimetry technique examined is dicentric chromosome aberrations (DCA). The physical dosimetry techniques include electron paramagnetic resonance (EPR) of biological material (teeth) and physical material (smartphone screen glass), and optically stimulated luminescence (OSL) of electronic components (surface mount resistors) from mobile phones. Issues relating to calibration and interpretation of the data are discussed. An important conclusion of the analysis is that more research is critically needed to interpret the efficacy of the various methods. Included in this needed research are intercomparisons of the various methods in controlled experiments and the need to harmonize protocols. - Highlights: • Utility of bio- and physical dosimetry methods for emergency dosimetry triage. • Analysis of intercomparison data for different bio- and physical dosimetry methods. • The percentage of false positives and false negatives for a simulated IND event. • More research, especially intercomparisons, is required to reduce uncertainties.

  11. Paediatric doses from diagnostic radiology in Victoria

    International Nuclear Information System (INIS)

    Boal, T.J.; Cardillo, I.; Einsiedel, P.F.

    1998-01-01

    This study examines doses to paediatric patients from diagnostic radiology. Measurements were made at 29 hospitals and private radiology practices in the state of Victoria. Entrance skin doses in air were measured for the exposure factors used by hospital radiology departments and private radiology practices for a standard size 1, 5, 10 and 15 year old child, for the following procedures: chest AP/PA, lat; abdomen AP; pelvis AP; lumbar spine AP, lat; and skull AP, lat. There was a large range of doses for each particular procedure and age group. Factors contributing to the range of doses were identified. Guidance levels for paediatric radiology based on the third quartile value of the skin entrance doses have been recommended and are compared with guidance levels. Copyright (1998) Australasian Physical and Engineering Sciences in Medicine

  12. A review of radiology staff doses and dose monitoring requirements

    International Nuclear Information System (INIS)

    Martin, C. J.

    2009-01-01

    Studies of radiation doses received during X-ray procedures by radiology, cardiology and other clinical staff have been reviewed. Data for effective dose (E), and doses to the eyes, thyroid, hands and legs have been analysed. These data have been supplemented with local measurements to determine the most exposed part of the hand for monitoring purposes. There are ranges of 60-100 in doses to individual tissues reported in the literature for similar procedures at different centres. While ranges in the doses per unit dose-area product (DAP) are between 10 and 25, large variations in dose result from differences in the sensitivity of the X-ray equipment, the type of procedure and the operator technique, but protection factors are important in maintaining dose levels as low as possible. The influence of shielding devices is significant for determining the dose to the eyes and thyroid, and the position of the operator, which depends on the procedure, is the most significant factor determining doses to the hands. A second body dosemeter worn at the level of the collar is recommended for operators with high workloads for use in assessment of effective dose and the dose to the eye. It is proposed that the third quartile values from the distributions of dose per unit DAP identified in the review might be employed in predicting the orders of magnitude of doses to the eye, thyroid and hands, based on interventional operator workloads. Such dose estimates could be employed in risk assessments when reviewing protection and monitoring requirements. A dosemeter worn on the little finger of the hand nearest to the X-ray tube is recommended for monitoring the hand. (authors)

  13. Postulated accident conditions for air cleaning systems and radiological dose assessments for containment options

    International Nuclear Information System (INIS)

    Hilliard, R.K.; Postma, A.K.

    1975-01-01

    Ambient conditions and performance requirements for emergency air cleaning systems applicable to commercial LMFBR plants were studied. The focus of this study centered on aerosol removal under hypothetical core disruptive accident conditions. Effort completed includes a review of air cleaning systems related to LMFBR plants, selection of three reference containment system designs, postulation of the EACS design basis accident (EACS-DBA), analysis of thermal conditions resulting from the DBA, analysis of aerosol transport behavior following the DBA, and an estimate of bone dose at the site boundary for each of the reference plant designs. Reference plant concepts were a single containment system (e.g., FFTF), a double containment system (e.g., CRBRP with closed head compartment), and a containment-confinement design in which an inerted, sealed primary volume was located within a ventilated building whose exhaust was filtered. The reference design basis accident selected here involved release to the inner containment system of 1 percent of non-volatile solids and plutonium, 25 percent of core halogens, 25 percent of core volatile solids, 100 percent of core noble gases, 68 lbs of sodium vapor and 5000 lbs of liquid sodium. 13 references. (U.S.)

  14. Radiological dose assessment for bounding accident scenarios at the Critical Experiment Facility, TA-18, Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    1991-09-01

    A computer modeling code, CRIT8, was written to allow prediction of the radiological doses to workers and members of the public resulting from these postulated maximum-effect accidents. The code accounts for the relationships of the initial parent radionuclide inventory at the time of the accident to the growth of radioactive daughter products, and considers the atmospheric conditions at time of release. The code then calculates a dose at chosen receptor locations for the sum of radionuclides produced as a result of the accident. Both criticality and non-criticality accidents are examined

  15. Radiation dose assessments to support evaluations of radiological control levels for recycling or reuse of materials and equipment

    International Nuclear Information System (INIS)

    Hill, R.L.; Aaberg, R.L.; Baker, D.A.; Kennedy, W.E. Jr.

    1995-07-01

    Pacific Northwest Laboratory is providing Environmental Protection Support and Assistance to the USDOE, Office of Environmental Guidance. Air, Water, and Radiation Division. As part of this effort, PNL is collecting data and conducting technical evaluations to support DOE analyses of the feasibility of developing radiological control levels for recycling or reuse of metals, concrete, or equipment containing residual radioactive contamination from DOE operations. The radiological control levels will be risk-based, as developed through a radiation exposure scenario and pathway analysis. The analysis will include evaluation of relevant radionuclides, potential mechanisms of exposure, and both health and non-health-related impacts. The main objective of this report is to develop a methodology for establishing radiological control levels for recycle or reuse. This report provides the results of the radiation exposure scenario and pathway analyses for 42 key radionuclides generated during DOE operations that may be contained in metals or equipment considered for either recycling or reuse. The scenarios and information developed by the IAEA. Application of Exemption Principles to the Recycle and Reuse of Materials from Nuclear Facilities, are used as the initial basis for this study. The analyses were performed for both selected worker populations at metal smelters and for the public downwind of a smelter facility. Doses to the public downwind were estimated using the US (EPA) CAP88-PC computer code with generic data on atmospheric dispersion and population density. Potential non-health-related effects of residual activity on electronics and on film were also analyzed

  16. Radiation dose assessments to support evaluations of radiological control levels for recycling or reuse of materials and equipment

    Energy Technology Data Exchange (ETDEWEB)

    Hill, R.L.; Aaberg, R.L.; Baker, D.A.; Kennedy, W.E. Jr.

    1995-07-01

    Pacific Northwest Laboratory is providing Environmental Protection Support and Assistance to the USDOE, Office of Environmental Guidance. Air, Water, and Radiation Division. As part of this effort, PNL is collecting data and conducting technical evaluations to support DOE analyses of the feasibility of developing radiological control levels for recycling or reuse of metals, concrete, or equipment containing residual radioactive contamination from DOE operations. The radiological control levels will be risk-based, as developed through a radiation exposure scenario and pathway analysis. The analysis will include evaluation of relevant radionuclides, potential mechanisms of exposure, and both health and non-health-related impacts. The main objective of this report is to develop a methodology for establishing radiological control levels for recycle or reuse. This report provides the results of the radiation exposure scenario and pathway analyses for 42 key radionuclides generated during DOE operations that may be contained in metals or equipment considered for either recycling or reuse. The scenarios and information developed by the IAEA. Application of Exemption Principles to the Recycle and Reuse of Materials from Nuclear Facilities, are used as the initial basis for this study. The analyses were performed for both selected worker populations at metal smelters and for the public downwind of a smelter facility. Doses to the public downwind were estimated using the US (EPA) CAP88-PC computer code with generic data on atmospheric dispersion and population density. Potential non-health-related effects of residual activity on electronics and on film were also analyzed.

  17. Dosimetry in Interventional Radiology - Effective Dose Estimation

    International Nuclear Information System (INIS)

    Miljanic, S.; Buls, N.; Clerinx, P.; Jarvinen, H.; Nikodemova, D.; Ranogajec-Komor, M; D'Errico, F.

    2008-01-01

    Interventional radiological procedures can lead to significant radiation doses to patients and to staff members. In order to evaluate the personal doses with respect to the regulatory dose limits, doses measured by dosimeters have to be converted to effective doses (E). Measurement of personal dose equivalent Hp(10) using a single unshielded dosimeter above the lead apron can lead to significant overestimation of the effective dose, while the measurement with dosimeter under the apron can lead to underestimation. To improve the accuracy, measurements with two dosimeters, one above and the other under the apron have been suggested ( d ouble dosimetry ) . The ICRP has recommended that interventional radiology departments develop a policy that staff should wear two dosimeters. The aim of this study was to review the double dosimetry algorithms for the calculation of effective dose in high dose interventional radiology procedures. The results will be used to develop general guidelines for personal dosimetry in interventional radiology procedures. This work has been carried out by Working Group 9 (Radiation protection dosimetry of medical staff) of the CONRAD project, which is a Coordination Action supported by the European Commission within its 6th Framework Program.(author)

  18. Radiological dose and metadata management

    International Nuclear Information System (INIS)

    Walz, M.; Madsack, B.; Kolodziej, M.

    2016-01-01

    This article describes the features of management systems currently available in Germany for extraction, registration and evaluation of metadata from radiological examinations, particularly in the digital imaging and communications in medicine (DICOM) environment. In addition, the probable relevant developments in this area concerning radiation protection legislation, terminology, standardization and information technology are presented. (orig.) [de

  19. Application of Biota Dose Assessment Committee Methodology to Assess Radiological Risk to Salmonids in the Hanford Reach of the Columbia River

    International Nuclear Information System (INIS)

    Poston, Ted M.; Antonio, Ernest J.; Peterson, Robert E.

    2002-01-01

    Protective guidance for biota in the U.S. Department of Energy's Graded Approach for Evaluating Radiation Doses to Aquatic and Terrestrial Biota is based on population level protection guides of 10 or 1 mGy.d-1, respectively. Several 'ecologically significant units' of Pacific salmon are listed under the Endangered Species Act. The Middle Columbia Steelhead unit is endangered and the adult steelhead spawn in the reach. The reach also supports one of the largest spawning populations of fall chinook salmon in the Northwest. The existence of the major spawning areas in the Hanford Reach has focused considerable attention on their ecological health by the U.S. Department of Energy, other federal and state regulatory agencies, and special interest groups. Dose assessments for developing salmonid embryos were performed for the hypothetical exposure to tritium, strontium-90, technetium-99, iodine-129, and uranium isotopes at specific sites on the Hanford Reach. These early life stages are potentially exposed in some areas of the Hanford Reach to radiological contaminants that enter the river via shoreline seeps and upwelling through the river substrate. At the screening level, one site approached the dose guideline of 10 mGy.d-1 established with the RAD-BCG methodology and exceeded a precautionary benchmark of 2.5 mGy.d-1. Special status of listed species affords these populations more consideration when assessing potential impacts of exposure to radionuclides and other contaminants associated with the Hanford Site operations. The evolution of dose benchmarks for aquatic organisms and consideration of precautionary principal and cumulative impacts are discussed in this paper.

  20. Radiological assessment of water treatment processes in a water treatment plant in Saudi Arabia: Water and sludge radium content, radon air concentrations and dose rates

    Energy Technology Data Exchange (ETDEWEB)

    Al-Jaseem, Q.Kh., E-mail: qjassem@kacst.edu.sa [Nuclear Science Research Institute (NSRI), King Abdulaziz City for Science and Technology (KACST), P.O. Box 6086, Riyadh 11442 (Saudi Arabia); Almasoud, Fahad I. [Nuclear Science Research Institute (NSRI), King Abdulaziz City for Science and Technology (KACST), P.O. Box 6086, Riyadh 11442 (Saudi Arabia); Ababneh, Anas M. [Physics Dept., Faculty of Science, Islamic University in Madinah, Al-Madinah, P.O. Box 170 (Saudi Arabia); Al-Hobaib, A.S. [Nuclear Science Research Institute (NSRI), King Abdulaziz City for Science and Technology (KACST), P.O. Box 6086, Riyadh 11442 (Saudi Arabia)

    2016-09-01

    There is an increase demand for clean water sources in Saudi Arabia and, yet, renewable water resources are very limited. This has forced the authorities to explore deep groundwater which is known to contain large concentrations of radionuclides, mainly radium isotopes. Lately, there has been an increase in the number of water treatment plants (WTPs) around the country. In this study, a radiological assessment of a WTP in Saudi Arabia was performed. Raw water was found to have total radium activity of 0.23 Bq/L, which exceeds the international limit of 0.185 Bq/L (5 pCi/L). The WTP investigated uses three stages of treatment: flocculation/sedimentation, sand filtration and reverse osmosis. The radium removal efficiency was evaluated for each stage and the respective values were 33%, 22% and 98%. Moreover, the activity of radium in the solid waste generated from the WTP in the sedimentation and sand filtrations stages were measured and found to be 4490 and 6750 Bq/kg, respectively, which exceed the national limit of 1000 Bq/kg for radioactive waste. A radiological assessment of the air inside the WTP was also performed by measuring the radon concentrations and dose rates and were found in the ranges of 2–18 Bq/m{sup 3} and 70–1000 nSv/h, respectively. The annual effective dose was calculated and the average values was found to be 0.3 mSv which is below the 1 mSv limit. - Highlights: • Radiological assessment of groundwater treatment plant was performed. • Radium Removal efficiency was calculated for different stages during water treatment. • Radium concentrations in sludge were measured and found to exceed the national limit for radioactive waste. • Air radon concentrations and dose rates were monitored in the water treatment plant. • The Reverse Osmosis (RO) unit was found to record the highest air radon concentrations and dose rates.

  1. Enjebi Island dose assessment

    International Nuclear Information System (INIS)

    Robison, W.L.; Conrado, C.L.; Phillips, W.A.

    1987-07-01

    We have updeated the radiological dose assessment for Enjebi Island at Enewetak Atoll using data derived from analysis of food crops grown on Enjebi. This is a much more precise assessment of potential doses to people resettling Enjebi Island than the 1980 assessment in which there were no data available from food crops on Enjebi. Details of the methods and data used to evaluate each exposure pathway are presented. The terrestrial food chain is the most significant potential exposure pathway and 137 Cs is the radionuclide responsible for most of the estimated dose over the next 50 y. The doses are calculated assuming a resettlement date of 1990. The average wholebody maximum annual estimated dose equivalent derived using our diet model is 166 mremy;the effective dose equivalent is 169 mremy. The estimated 30-, 50-, and 70-y integral whole-body dose equivalents are 3.5 rem, 5.1 rem, and 6.2 rem, respectively. Bone-marrow dose equivalents are only slightly higher than the whole-body estimates in each case. The bone-surface cells (endosteal cells) receive the highest dose, but they are a less sensitive cell population and are less sensitive to fatal cancer induction than whole body and bone marrow. The effective dose equivalents for 30, 50, and 70 y are 3.6 rem, 5.3 rem, and 6.6 rem, respectively. 79 refs., 17 figs., 24 tabs

  2. Comparison of the regulatory models assessing off-site radiological dose due to the routine releases of tritium

    International Nuclear Information System (INIS)

    Hwang, W. T.; Kim, E. H.; Han, M. H.; Choi, Y. H.; Lee, H. S.; Lee, C. W.

    2005-01-01

    Methodologies of NEWTRIT model, NRC model and AIRDOS-EPA model, which are off-site dose assessment models for regulatory compliance from routine releases of tritium into the environment, were investigated. Using the domestic data, if available, the predictive results of the models were compared. Among them, recently developed NEWTRIT model considers only doses from organically bounded tritium (OBT) due to environmental releases of tritiated water (HTO). A total dose from all exposure pathways predicted from AIRDOS-EPA model was 1.03 and 2.46 times higher than that from NEWTRIT model and NRC model, respectively. From above result, readers should not have an understanding that a predictive dose from NRC model may be underestimated compared with a realistic dose. It is because of that both mathematical models and corresponding parameter values for regulatory compliance are based on the conservative assumptions. For a dose by food consumption predicted from NEWTRIT model, the contribution of OBT was nearly equivalent to that of HTO due to relatively high consumption of grains in Korean. Although a total dose predicted from NEWTRIT model is similar to that from AIRDOS-EPA model, NEWTRIT model may be have a meaning in the understanding of phenomena for the behavior of HTO released into the environment

  3. Metrology of radiation doses in diagnostic radiology

    International Nuclear Information System (INIS)

    Leclet, H.

    2016-01-01

    This article recalls how to calculate effective and equivalent doses in radiology from the measured value of the absorbed dose. The 97/43 EURATOM directive defines irradiation standards for diagnostic radiology (NRD) as the value of the radiation dose received by the patient's skin when the diagnostic exam is performed. NRD values are standard values that can be exceeded only with right medical or technical reasons, they are neither limit values nor optimized values. The purpose of NRD values is to avoid the over-irradiation of patients and to homogenize radiologists' practices. French laws impose how and when radiologists have to calculate the radiation dose received by the patient's skin. The calculated values have to be compared with NRD values and any difference has to be justified. A table gives NRD values for all diagnostic exams. (A.C.)

  4. Managing patient dose in digital radiology

    International Nuclear Information System (INIS)

    2014-01-01

    Digital techniques have the potential to improve the practice of radiology but they also risk the overuse of radiation. The main advantages of digital imaging, i.e. wide dynamic range, post processing, multiple viewing options, and electronic transfer and archiving possibilities, are clear but overexposures can occur without an adverse impact on image quality. In conventional radiography, excessive exposure produces a black film. In digital systems, good images are obtained for a large range of doses. It is very easy to obtain (and delete) images with digital fluoroscopy systems, and there may be a tendency to obtain more images than necessary. In digital radiology, higher patient dose usually means improved image quality, so a tendency to use higher patient doses than necessary could occur. Different medical imaging tasks require different levels of image quality, and doses that have no additional benefit for the clinical purpose should be avoided. Image quality can be compromised by inappropriate levels of data compression and/or post processing techniques. All these new challenges should be part of the optimisation process and should be included in clinical and technical protocols. Local diagnostic reference levels should be re-evaluated for digital imaging, and patient dose parameters should be displayed at the operator console. Frequent patient dose audits should occur when digital techniques are introduced. Training in the management of image quality and patient dose in digital radiology is necessary. Digital radiology will involve new regulations and invoke new challenges for practitioners. As digital images are easier to obtain and transmit, the justification criteria should be reinforced. Commissioning of digital systems should involve clinical specialists, medical physicists, and radiographers to ensure that imaging capability and radiation dose management are integrated. Quality control requires new procedures and protocols (visualisation, transmission

  5. Radiological assessment of NORM industries in Ireland-radiation doses to workers and members of the public

    International Nuclear Information System (INIS)

    Organo, C.; Fenton, D.

    2008-12-01

    only those industries with potential NORM issues were first published by the European Commission in 1997 and were followed by more specific guidance documents covering particular aspects of NORM: building materials, remediation of contaminated sites, NORM effluents and discharges, waste types produced by industries dealing with special metal and ceramics and NORM waste management and treatment options. Countries located outside Europe may follow and/or implement the International Atomic Energy Agency (IAEA) Safety Standards requirements. As far as the identification of work activities involving NORM is concerned, the IAEA has equally produced a number of important and very helpful documents in the recent years, complementary to those published by the EC which capture the essential aspects of the approach advocated by the IAEA to identify NORM industries. Four large industries operating in Ireland and dealing with NORM were prioritised and investigated to determine the level of radiation to which workers and members of the public were exposed as a result of their work practices: the peat-fired power production, the coal-fired power production, the extraction of natural gas and the bauxite refining for the production of alumina. In each case, a thorough examination of the industrial process has been carried out to identify the potential radiation exposure situations arising from the occurrance of NORM at the different stages of the respective process. At the core of our assessment methodology, the following aspects were targeted. The potential for enhancement of radionuclide concentrations above their natural levels in products, by-products, residues and waste. Their availability to be released into the biosphere, due to physicochemical changes during processing or due to the method used to manage the residues and the waste produced. Occupational radiation doses were estimated based on field measurements and analysis of samples collected onsite. For particular scenarios

  6. Factors affecting patient dose in diagnostic radiology

    International Nuclear Information System (INIS)

    Poletti, J.L.

    1985-01-01

    There are two stages in the X-ray image forming process; first the irradiation of the patient to produce the X-ray pattern in space, known as the primary radiological image, and second, the conversion of this pattern into a visible form. This report discusses the first stage and its interrelation with image quality and patient dose

  7. Estimation of the radiological background and dose assessment in areas with naturally occurring uranium geochemical anomalies—a case study in the Iberian Massif (Central Portugal)

    International Nuclear Information System (INIS)

    Pereira, A.J.S.C.; Neves, L.J.P.F.

    2012-01-01

    Naturally occurring uranium geochemical anomalies, representative of the several thousand recognized in the Portuguese section of the Iberian Massif and outcropping in three target areas with a total of a few thousand square metres, were subjected to a detailed study (1:1000 scale) to evaluate the radiological health-risk on the basis of a dose assessment. To reach this goal some radioactive isotopes from the uranium, thorium and potassium radioactive series were measured in 52 samples taken from different environmental compartments: soils, stream sediments, water, foodstuff (vegetables) and air; external radiation was also measured through a square grid of 10 × 10 m, with a total of 336 measurements. The results show that some radioisotopes have high activities in all the environmental compartments as well as a large variability, namely for those of the uranium decay chain, which is a common situation in the regional geological setting. Isotopic disequilibrium is also common and led to an enrichment of several isotopes in the different pathways, as is the case of 226 Ra; maximum values of 1.76 Bq L −1 (water), 986 Bq kg −1 (soils) and 18.9 Bq kg −1 (in a turnip sample) were measured. On the basis of a realistic scenario combined with the experimental data, the effective dose from exposure to ionizing radiation for two groups of the population (rural and urban) was calculated; the effective dose is variable between 8.0 and 9.5 mSv year −1 , which is 3–4 times higher than the world average. Thus, the radiological health-risk for these populations could be significant and the studied uranium anomalies must be taken into account in the assessment of the geochemical background. The estimated effective dose can also be used as typical of the background of the Beiras uranium metalogenetic province and therefore as a “benchmark” in the remediation of the old uranium mining sites. - Highlights: ► The importance of small-sized naturally occurring uranium

  8. Evaluations of gonad and fetal doses for diagnostic radiology.

    Science.gov (United States)

    Tung, C J; Tsai, H Y

    1999-07-01

    A national survey of patient doses for diagnostic radiology was planned in the Republic of China. We performed a pilot study for this survey to develop a protocol of the dose assessments. Entrance skin doses and organ (including ovary, testicle and uterus) doses were measured by thermoluminescent dosimeters and calculated by means of Monte Carlo simulations for several diagnostic procedures. We derived a formula and used the RadComp software for the computation of entrance skin doses. This formula involves several factors, such as kVp, mAs, the focus-to-skin-distance and aluminum filtration. RadComp software was applied to obtain free-air entrance exposures which were converted to entrance skin doses by considering the backscattering radiation from the body. Organ doses were measured using a RANDO phantom and calculated using a mathematical phantom for several diagnostic examinations. Genetically significant doses were calculated from ovary and testicle doses for the evaluation of hereditary effects. Embryo/fetal doses were determined from the uterine doses by considering the increase in uterus size with gestational age. We found that the patient doses studied in this work were all below the reference doses recommended by the National Radiological Protection Board of the U.K.

  9. Radiological dose assessment for residual radioactive material in soil at the clean slate sites 1, 2, and 3, Tonopah Test Range

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-06-01

    A radiological dose assessment has been performed for Clean Slate Sites 1, 2, and 3 at the Tonopah Test Range, approximately 390 kilometers (240 miles) northwest of Las Vegas, Nevada. The assessment demonstrated that the calculated dose to hypothetical individuals who may reside or work on the Clean Slate sites, subsequent to remediation, does not exceed the limits established by the US Department of Energy for protection of members of the public and the environment. The sites became contaminated as a result of Project Roller Coaster experiments conducted in 1963 in support of the US Atomic Energy Commission (Shreve, 1964). Remediation of Clean Slate Sites 1, 2, and 3 is being performed to ensure that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works on a Clean Slate site should not exceed 100 millirems per year. The DOE residual radioactive material guideline (RESRAD) computer code was used to assess the dose. RESRAD implements the methodology described in the DOE manual for establishing residual radioactive material guidelines (Yu et al., 1993a). In May and June of 1963, experiments were conducted at Clean Slate Sites 1, 2, and 3 to study the effectiveness of earth-covered structures for reducing the dispersion of nuclear weapons material as a result of nonnuclear explosions. The experiments required the detonation of various simulated weapons using conventional chemical explosives (Shreve, 1964). The residual radioactive contamination in the surface soil consists of weapons grade plutonium, depleted uranium, and their radioactive decay products.

  10. Radiological dose assessment for residual radioactive material in soil at the clean slate sites 1, 2, and 3, Tonopah Test Range

    International Nuclear Information System (INIS)

    1997-06-01

    A radiological dose assessment has been performed for Clean Slate Sites 1, 2, and 3 at the Tonopah Test Range, approximately 390 kilometers (240 miles) northwest of Las Vegas, Nevada. The assessment demonstrated that the calculated dose to hypothetical individuals who may reside or work on the Clean Slate sites, subsequent to remediation, does not exceed the limits established by the US Department of Energy for protection of members of the public and the environment. The sites became contaminated as a result of Project Roller Coaster experiments conducted in 1963 in support of the US Atomic Energy Commission (Shreve, 1964). Remediation of Clean Slate Sites 1, 2, and 3 is being performed to ensure that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works on a Clean Slate site should not exceed 100 millirems per year. The DOE residual radioactive material guideline (RESRAD) computer code was used to assess the dose. RESRAD implements the methodology described in the DOE manual for establishing residual radioactive material guidelines (Yu et al., 1993a). In May and June of 1963, experiments were conducted at Clean Slate Sites 1, 2, and 3 to study the effectiveness of earth-covered structures for reducing the dispersion of nuclear weapons material as a result of nonnuclear explosions. The experiments required the detonation of various simulated weapons using conventional chemical explosives (Shreve, 1964). The residual radioactive contamination in the surface soil consists of weapons grade plutonium, depleted uranium, and their radioactive decay products

  11. Environmental Tools and Radiological Assessment

    Science.gov (United States)

    This presentation details two tools (SADA and FRAMES) available for use in environmental assessments of chemicals that can also be used for radiological assessments of the environment. Spatial Analysis and Decision Assistance (SADA) is a Windows freeware program that incorporate...

  12. Work practices and occupational radiation dose among radiologic technologists in Korea

    International Nuclear Information System (INIS)

    Cha, Eun Shil; Lee, Won Jin; Ha, Mina; Hwang, Seung Sik; Lee, Kyoung Mu; Jeong, Mee Seon

    2013-01-01

    Radiologic technologists are one of the occupational groups exposed to the highest dose of radiation worldwide. In Korea, radiologic technologists occupy the largest group (about 33%) among medical radiation workers and they are exposed to the highest dose of occupational dose of radiation as well (1). Although work experience with diagnostic radiation procedure of U.S. radiologic technologists was reported roughly (2), few studies have been conducted for description of overall work practices and the change by calendar year and evaluation of related factors on occupational radiation dose. The aims of the study are to describe work practices and to assess risk factors for occupational radiation dose among radiologic technologists in Korea. This study showed the work practices and occupational radiation dose among representative sample of radiologic technologists in Korea. The annual effective dose among radiologic technologists in Korea remains higher compared with those of worldwide average and varied according to demographic factors, year began working, and duration of working

  13. Introduction to radiological performance assessment

    International Nuclear Information System (INIS)

    Moss, G.

    1995-02-01

    A radiological performance assessment is conducted to provide reasonable assurance that performance objectives for low-level radioactive waste (LLW) disposal will be met. Beginning in the early stages of development, a radiological performance assessment continues through the operational phase, and is instrumental in the postclosure of the facility. Fundamental differences exist in the regulation of commercial and defense LLW, but the radiological performance assessment process is essentially the same for both. The purpose of this document is to describe that process in a concise and straightforward manner. This document focuses on radiological performance assessment as it pertains to commercial LLW disposal, but is applicable to US Department of Energy sites as well. Included are discussions on performance objectives, site characterization, and how a performance assessment is conducted. A case study is used to illustrate how the process works as a whole. A bibliography is provided to assist in locating additional information

  14. Doses from Hiroshima mass radiologic gastric surveys

    Energy Technology Data Exchange (ETDEWEB)

    Antoku, S; Sawada, S; Russell, W J [Radiation Effects Research Foundation, Hiroshima (Japan)

    1980-05-01

    Doses to examinees from mass radiologic surveys of the stomach in Hiroshima Perfecture were estimated by surveying for the frequency of the examinations, and for the technical factors used in them, and by phantom dosimetry. The average surface, active bone marrow and male and female gonad doses per examination were 5.73 rad, 231 mrad, and 20.6 and 140 mrad, respectively. These data will be used in estimating doses from medical X-rays among atomic bomb survivors. By applying them to the Hiroshima population, the genetically significant, per caput mean marrow, and leukemia significant doses were 0.14,8.6 and 7.4 mrad, respectively. There was a benefit-to risk ratio of about 50 for mass gastric surveys performed in 1976. However, the calculated risk was greater than the benefit for examinees under 29 years of age because of the lower incidence of gastric cancer in those under 29 years.

  15. EcoDoses. Improving radiological assessment of doses to man from terrestrial ecosystems: A status report for the NKS-B activity 2006

    Energy Technology Data Exchange (ETDEWEB)

    Nielsen, S.; Andersson, K.G. (Technical Univ. of Denmark, Risoe National Lab. for Sustainable Energy, Roskilde (Denmark)); Thoerring, H.; Liland, A. (Norwegian Radiation Protection Authority (Norway)); Joensen, H.P. (Frooskaparsetur Foeroya, Faroe Islands, Torshavn (Denmark)); Isaksson, M. (Goeteborg Univ. (Sweden)); Saxen, R.; Kostiainen, E. (Radiation and Nuclear Safety Authority (STUK) (Finland)); Suolanen, V. (VTT Technical Research Centre of Finland, Espoo (Finland)); Palsson, S.E. (Geislavarnir rikisins (Iceland))

    2009-03-15

    The overall aim of the NKS-B EcoDoses activity is to improve the prediction of doses to humans from consumption of radioactively contaminated food. For this purpose, various published and unpublished datasets have been compiled and applied in developing refined parameterisation for existing food dose models. The ECOSYS model developed in Germany after the Chernobyl accident has been applied as the basis for the investigations. This model can be operated both with discrete releases adequately representing a nuclear power plant accident, and with continuous or multiple releases, as observed in the nuclear weapons testing period. The modelling has revealed that it is essential to ensure that case-specific values are applied for a range of parameters, adequately reflecting the actual conditions with respect to geology, season, climate and demography. In connection with this year's work on the activity, sensitivity studies have been conducted with the ECOSYS model, in which the influence on ingestion dose estimates of a number of parameters has been evaluated in relation to Faroese conditions. The importance of applying location specific data to estimate dose is pinpointed, and it is also concluded that dose predictions for a small and distinct area like the Faroese, where not all of the many parameters required to run ECOSYS optimally have been adequately assessed in recent years, can be associated with considerable uncertainty. A Finnish study has been made in relation to modelling of radiocaesium behaviour in lakes. This study was carried out using a compartmental model that is included as a module in the DETRA dose assessment tool. A total of nine different input parameters (distribution coefficients, run-off from the catchment, erosion from the catchment, sedimentation rate in the lakes, lake water exchange rate, and biological half-lives in four fish species) were varied, and particularly distribution coefficients and lake water exchange rates were

  16. EcoDoses. Improving radiological assessment of doses to man from terrestrial ecosystems: A status report for the NKS-B activity 2006

    International Nuclear Information System (INIS)

    Nielsen, S.; Andersson, K.G.; Thoerring, H.; Liland, A.; Joensen, H.P.; Isaksson, M.; Saxen, R.; Kostiainen, E.; Suolanen, V.; Palsson, S.E.

    2009-03-01

    The overall aim of the NKS-B EcoDoses activity is to improve the prediction of doses to humans from consumption of radioactively contaminated food. For this purpose, various published and unpublished datasets have been compiled and applied in developing refined parameterisation for existing food dose models. The ECOSYS model developed in Germany after the Chernobyl accident has been applied as the basis for the investigations. This model can be operated both with discrete releases adequately representing a nuclear power plant accident, and with continuous or multiple releases, as observed in the nuclear weapons testing period. The modelling has revealed that it is essential to ensure that case-specific values are applied for a range of parameters, adequately reflecting the actual conditions with respect to geology, season, climate and demography. In connection with this year's work on the activity, sensitivity studies have been conducted with the ECOSYS model, in which the influence on ingestion dose estimates of a number of parameters has been evaluated in relation to Faroese conditions. The importance of applying location specific data to estimate dose is pinpointed, and it is also concluded that dose predictions for a small and distinct area like the Faroese, where not all of the many parameters required to run ECOSYS optimally have been adequately assessed in recent years, can be associated with considerable uncertainty. A Finnish study has been made in relation to modelling of radiocaesium behaviour in lakes. This study was carried out using a compartmental model that is included as a module in the DETRA dose assessment tool. A total of nine different input parameters (distribution coefficients, run-off from the catchment, erosion from the catchment, sedimentation rate in the lakes, lake water exchange rate, and biological half-lives in four fish species) were varied, and particularly distribution coefficients and lake water exchange rates were demonstrated to

  17. Radiation dose evaluation in patients submitted to conventional radiological examinations

    International Nuclear Information System (INIS)

    Tilly Junior, Joao G.

    1997-01-01

    This work presents the results of the evaluation of radiation dose delivered to the patients undergoing conventional radiological procedures. Based in the realized measurement some indicators are settled to quantitative appraisal of the radiological protection conditions offered to the population. Data assessment was done in the county of Curitiba, in Parana State, Brazil, from 12/95 to 04/96, in ten rooms of three different institutions, under 101 patients, adults with 70 ± 10 kg, during real examinations of chest PA, chest LAT and abdomen AP. (author)

  18. Concepts of collective dose in radiological protection

    International Nuclear Information System (INIS)

    Lindell, B.

    1985-01-01

    The collective dose (S) is the product of the number of individuals exposed and their average radiation dose. ''Radiation dose'' is usually taken to be the effective dose equivalent (Hsub(E)) as defined by the ICRP. The unit of the collective dose is then the man.sievert (man.Sv). The following four applications of the collective dose are the most common: (a) in the assessment of the highest per caput dose rate in the future from a continued practice which exposes some critical group or the population as a whole to radiation; (b) in the limitation of present radiation sources, if it is believed that additional sources in the future may add to the per caput dose in a population so that it might reach unacceptable levels unless all sources are controlled at an early stage; (c) as an input to justification assessments, indicating the total detriment from a certain practice; and (d) as an input to optimization assessments as the basis for costing detriment in differential cost-benefit analyses of protection arrangements. It is sometimes said that the collective dose is a useful quantity only if the assumption of a non-threshold, linear dose-response relation is valid. This assumption is not always necessary. Applications (a) and (b) are possible without any assumption on the dose-response relationship at very low doses. Only applications (c) and (d) require the assumption of a non-threshold, linear dose-response relation. Some hesitation in using the collective dose originates in distrust in the biological assumptions implied by uses (c) and (d), but also in lack of confidence in the meaningfulness of collective doses that have been derived by adding dose contributions over very long time periods. However, none of the four applications (a) - (d) is by necessity related to extreme time scales. That problem mainly arises in the assessment of radioactive waste repositories

  19. Radiological assessment of water treatment processes in a water treatment plant in Saudi Arabia: Water and sludge radium content, radon air concentrations and dose rates.

    Science.gov (United States)

    Al-Jaseem, Q Kh; Almasoud, Fahad I; Ababneh, Anas M; Al-Hobaib, A S

    2016-09-01

    There is an increase demand for clean water sources in Saudi Arabia and, yet, renewable water resources are very limited. This has forced the authorities to explore deep groundwater which is known to contain large concentrations of radionuclides, mainly radium isotopes. Lately, there has been an increase in the number of water treatment plants (WTPs) around the country. In this study, a radiological assessment of a WTP in Saudi Arabia was performed. Raw water was found to have total radium activity of 0.23Bq/L, which exceeds the international limit of 0.185Bq/L (5pCi/L). The WTP investigated uses three stages of treatment: flocculation/sedimentation, sand filtration and reverse osmosis. The radium removal efficiency was evaluated for each stage and the respective values were 33%, 22% and 98%. Moreover, the activity of radium in the solid waste generated from the WTP in the sedimentation and sand filtrations stages were measured and found to be 4490 and 6750Bq/kg, respectively, which exceed the national limit of 1000Bq/kg for radioactive waste. A radiological assessment of the air inside the WTP was also performed by measuring the radon concentrations and dose rates and were found in the ranges of 2-18Bq/m(3) and 70-1000nSv/h, respectively. The annual effective dose was calculated and the average values was found to be 0.3mSv which is below the 1mSv limit. Copyright © 2016 Elsevier B.V. All rights reserved.

  20. Measurement of radiation dose in dental radiology

    International Nuclear Information System (INIS)

    Helmrot, E.; Carlsson, G. A.

    2005-01-01

    Patient dose audit is an important tool for quality control and it is important to have a well-defined and easy to use method for dose measurements. In dental radiology, the most commonly used dose parameters for the setting of diagnostic reference levels (DRLs) are the entrance surface air kerma (ESAK) for intraoral examinations and dose width product (DWP) for panoramic examinations. DWP is the air kerma at the front side of the secondary collimator integrated over the collimator width and an exposure cycle. ESAK or DWP is usually measured in the absence of the patient but with the same settings of tube voltage (kV), tube current (mA) and exposure time as with the patient present. Neither of these methods is easy to use, and, in addition, DWP is not a risk related quantity. A better method of monitoring patient dose would be to use a dose area product (DAP) meter for all types of dental examinations. In this study, measurements with a DAP meter are reported for intraoral and panoramic examinations. The DWP is also measured with a pencil ionisation chamber and the product of DWP and the height H (DWP x H) of the secondary collimator (measured using film) was compared to DAP. The results show that it is feasible to measure DAP using a DAP meter for both intraoral and panoramic examinations. The DAP is therefore recommended for the setting of DRLs. (authors)

  1. Factors affecting patient dose in diagnostic radiology

    International Nuclear Information System (INIS)

    Poletti, J.L.

    1994-03-01

    The report, Factors Affecting Patient Dose in Diagnostic Radiology is divided into three main sections. Part one is introductory and covers the basic principles of x-ray production and image formation. It includes discussion of x-ray generators and x-ray tubes, radiation properties and units, specification and measurement of x-ray beams, methods of patient dose measurement, radiation effects, radiation protection philosophy and finally the essentials of imaging systems. Part two examines factors affecting the x-ray output of x-ray machines and the characteristics of x-ray beams. These include the influence of heat ratings, kVp, waveform, exposure timer, filtration, focus-film distance, beam intensity distribution, x-ray tube age and focal spot size. Part three examines x-ray machine, equipment and patient factors which affect the dose received by individual patients. The factors considered include justification of examinations, choice of examination method, film/screen combinations, kVp, mAs, focus-film distance, collimation and field size, exposure time, projection, scatter, generator calibration errors, waveform, filtration, film processing and patient size. The patient dose implications of fluoroscopy systems, CT scanners, special procedures and mammography are also discussed. The report concludes with a brief discussion of patient dose levels in New Zealand and dose optimisation. 104 refs., 32 figs., 27 tabs

  2. [Evaluation of patient doses in interventional radiology].

    Science.gov (United States)

    Ropolo, R; Rampado, O; Isoardi, P; Gandini, G; Rabbia, C; Righi, D

    2001-01-01

    To verify the suitability of indicative quantities to evaluate the risk related to patient exposure, in abdominal and vascular interventional radiology, by the study of correlations between dosimetric quantities and other indicators. We performed in vivo measurements of entrance skin dose (ESD) and dose area product (DAP) during 48 procedures to evaluate the correlation among dosimetric quantities, and an estimation of spatial distribution of exposure and effective dose (E). To measure DAP we used a transmission ionization chamber and to evaluate ESD and its spatial distribution we used radiographic film packed in a single envelope and placed near the patient's skin. E was estimated by a calculation software using data from film digitalisation. From the data derived for measurements in 27 interventional procedures on 48 patients we obtained a DAP to E conversion factor of 0.15 mSv / Gy cm2, with an excellent correlation (r=.99). We also found a good correlation between DAP and exposure parameters such as fluoroscopy time and number of images. The greatest effective dose was evaluated for a multiple procedure in the hepatic region, with a DAP value of 425 Gy cm2. The greatest ESD was about 550 mGy. For groups of patients undergoing similar interventional procedures the correlation between ESD and DAP had conversion factors from 6 to 12 mGy Gy-1 cm-2. The evaluation of ESD and E by slow films represents a valid method for patient dosimetry in interventional radiology. The good correlation between DAP and fluoroscopy time and number of images confirm the suitability of these indicators as basic dosimetric information. All the ESD values found are lower than threshold doses for deterministic effects.

  3. CALDoseX-a software tool for the assessment of organ and tissue absorbed doses, effective dose and cancer risks in diagnostic radiology

    International Nuclear Information System (INIS)

    Kramer, R; Khoury, H J; Vieira, J W

    2008-01-01

    CALDose X is a software tool that provides the possibility of calculating incident air kerma (INAK) and entrance surface air kerma (ESAK), two important quantities used in x-ray diagnosis, based on the output of the x-ray equipment. Additionally, the software uses conversion coefficients (CCs) to assess the absorbed dose to organs and tissues of the human body, the effective dose as well as the patient's cancer risk for radiographic examinations. The CCs, ratios between organ or tissue absorbed doses and measurable quantities, have been calculated with the FAX06 and the MAX06 phantoms for 34 projections of 10 commonly performed x-ray examinations, for 40 combinations of tube potential and filtration ranging from 50 to 120 kVcp and from 2.0 to 5.0 mm aluminum, respectively, for various field positions, for 29 selected organs and tissues and simultaneously for the measurable quantities, INAK, ESAK and kerma area product (KAP). Based on the x-ray irradiation parameters defined by the user, CALDose X shows images of the phantom together with the position of the x-ray beam. By using true to nature voxel phantoms, CALDose X improves earlier software tools, which were mostly based on mathematical MIRD5-type phantoms, by using a less representative human anatomy.

  4. Radiation dose to physicians’ eye lens during interventional radiology

    International Nuclear Information System (INIS)

    Bahruddin, N A; Hashim, S; Karim, M K A; Ang, W C; Salehhon, N; Sabarudin, A; Bakar, K A

    2016-01-01

    The demand of interventional radiology has increased, leading to significant risk of radiation where eye lens dose assessment becomes a major concern. In this study, we investigate physicians' eye lens doses during interventional procedures. Measurement were made using TLD-100 (LiF: Mg, Ti) dosimeters and was recorded in equivalent dose at a depth of 0.07 mm, Hp(0.07). Annual Hp(0.07) and annual effective dose were estimated using workload estimation for a year and Von Boetticher algorithm. Our results showed the mean Hp(0.07) dose of 0.33 mSv and 0.20 mSv for left and right eye lens respectively. The highest estimated annual eye lens dose was 29.33 mSv per year, recorded on left eye lens during fistulogram procedure. Five physicians had exceeded 20 mSv dose limit as recommended by international commission of radiological protection (ICRP). It is suggested that frequent training and education on occupational radiation exposure are necessary to increase knowledge and awareness of the physicians’ thus reducing dose during the interventional procedure. (paper)

  5. Predictions of models for environmental radiological assessment

    International Nuclear Information System (INIS)

    Peres, Sueli da Silva; Lauria, Dejanira da Costa; Mahler, Claudio Fernando

    2011-01-01

    In the field of environmental impact assessment, models are used for estimating source term, environmental dispersion and transfer of radionuclides, exposure pathway, radiation dose and the risk for human beings Although it is recognized that the specific information of local data are important to improve the quality of the dose assessment results, in fact obtaining it can be very difficult and expensive. Sources of uncertainties are numerous, among which we can cite: the subjectivity of modelers, exposure scenarios and pathways, used codes and general parameters. The various models available utilize different mathematical approaches with different complexities that can result in different predictions. Thus, for the same inputs different models can produce very different outputs. This paper presents briefly the main advances in the field of environmental radiological assessment that aim to improve the reliability of the models used in the assessment of environmental radiological impact. The intercomparison exercise of model supplied incompatible results for 137 Cs and 60 Co, enhancing the need for developing reference methodologies for environmental radiological assessment that allow to confront dose estimations in a common comparison base. The results of the intercomparison exercise are present briefly. (author)

  6. Evaluation of the radiological quality of the water on Bikini and Eneu Islands in 1975: dose assessment based on initial sampling

    International Nuclear Information System (INIS)

    Noshkin, V.E.; Robison, W.L.; Wong, K.M.; Eagle, R.J.

    1977-01-01

    This report describes the radiological quality of the groundwater on the two main islands (Eneu and Bikini) of Bikini Atoll during June 1975 (from data obtained from water samples collected at old and new well sites on both islands) and the cistern water on Bikini Island. Based on analyses of these samples, we found that the cistern water from Bikini Island is both chemically and radiologically acceptable as drinking water in accordance with standard limits established by the U.S. Public Health Service. However, on both islands the quality of the groundwater varied from one site to another. At some wells both chemical and radiological quality are acceptable; at others one or both are unacceptable according to U.S. Public Health Standards. The doses we predict from consumption of both cistern and groundwater are acceptable under federal guidelines. However, doses predicted from consumption of groundwater are high enough to warrant careful evaluation of other potential exposure pathways

  7. A comparison of the radiological doses to man predicted by the MILDOS, UDAD, and UMMAC assessment codes

    International Nuclear Information System (INIS)

    Polehn, J.L.; Coleman, J.H.

    1984-01-01

    The output of three computer codes used to estimate the dose to man from uranium mining and milling operations are compared. UMMAC was developed by the Tennessee Valley Authority. UDAD (version 9) was developed at the Argonne National Laboratory. Version 4 of UDAD was modified by the Nuclear Regulatory Commission and renamed MILDOS. Dose estimates vary widely between the three codes. However, it appears any of the codes can be used if care is taken in the analyses of the output

  8. Radiological dose assessment for the decontaminated concrete removed from 183-H solar evaporation basins at the Hanford site, Richland, Washington

    International Nuclear Information System (INIS)

    Kamboj, S.; Faillace, E.; Yu, C.

    1997-01-01

    Potential maximum radiation dose rates over a 1,000-year time horizon were calculated for exposure to the decontaminated concrete removed from the 183-H Solar Evaporation Basins at the Hanford Site, Richland, Washington. The RESRAD computer code, Version 5.62, which implements the methodology described in the US Department of Energy's manual for developing residual radioactive material guidelines, was used in this evaluation. Currently, the concrete is not being used. Four potential exposure scenarios were developed for the land area where the decontaminated concrete will be stored. In Scenario A industrial use of the land is assumed; in Scenario B recreational use of the land is assumed; in Scenario C residential use of the land is assumed; and in Scenario D (a plausible but unlikely land-use scenario), the presence of a subsistence farmer in the immediate vicinity of the land is assumed. For Scenarios A and B, water used for drinking is assumed to be surface water from the Columbia River; for Scenarios C and D, groundwater drawn from a well located at the downgradient edge of the storage area is the only source of water for drinking, irrigation, and raising livestock. Conservative parameters values were used to estimate the radiation doses. The results of the evaluation indicate that the US Department of Energy's dose limit of 100 mrem/yr would not be exceeded for any of the scenarios analyzed. The potential maximum dose rates for Scenarios A, B, C, and D are 0.75, 0.022, 29, 29 mrem/yr, respectively. An uncertainty analysis was performed to determine which parameters have the greatest impact on the estimated doses. The doses in Scenarios C and D were found to be very sensitive to the magnitude of the irrigation rate

  9. Radiological assessments for the National Ignition Facility

    International Nuclear Information System (INIS)

    Hong, Kou-John; Lazaro, M.A.

    1996-01-01

    The potential radiological impacts of the National Ignition Facility (NIF), a proposed facility for fusion ignition and high energy density experiments, were assessed for five candidate sites to assist in site selection. The GENII computer program was used to model releases of radionuclides during normal NIF operations and a postulated accident and to calculate radiation doses to the public. Health risks were estimated by converting the estimated doses into health effects using a standard cancer fatality risk factor. The greatest calculated radiation dose was less than one thousandth of a percent of the dose received from natural background radiation; no cancer fatalities would be expected to occur in the public as the result of normal operations. The highest dose conservatively estimated to result from a postulated accident could lead to one in one million risk of cancer

  10. Radiological assessement of Crohn's disease

    International Nuclear Information System (INIS)

    Florio, F.; Palladino, M.; Stella, P.; Barbi, E.

    1987-01-01

    Fifty-eight consecutive cases of patients affected by Crohn's disease, with ileum (23/58), colon (10/58) and ileo-colic (25/58) involvement were studied. A good overall sensitivity was reached by the radiological procedures employed (barium meal, barium enema, enterclysis). Enterclysis is proposed as a second-step method for the study of ileum involvement, because it provides a quite precise assessement of disease stage and extent. Some criteria for a rational use of current radiological procedures in follow-up of both surgically and medically treated patients are proposed. Moreover it is suggested that better coordination of anatomo-radiological and clinical aspects could improve the therapeutic approach and prognostic judgement in such cases

  11. Radiation doses and correlated late effects in diagnostic radiology

    International Nuclear Information System (INIS)

    Gustafsson, M.

    1980-04-01

    Patient irradiation in diagnostic radiology was estimated from measurements of absorbed doses in different organs, assessment of the energy imparted and retrospective calculations based on literature data. Possible late biological effects, with special aspects on children, were surveyed. The dose to the lens of the eye and the possibility of shielding in carotid angiography was studied as was the absorbed dose to the thyroid gland at cardiac catheterization and angiocardiography in children. Calculations of the mean bone marrow dose and gonad doses were performed in children with chronic skeletal disease revealing large contributions from examinations of organs other than the skeleton. The dose distribution in the breast in mammography was investigated. Comparison of the energy imparted in common roentgen examinations in 1960 and 1975 showed an unexpected low decrease in spite of technical improvements. Reasons for the failing decrease are discussed. The energy imparted to children in urological examinations was reduced significantly due to introduction of high sensitivity screens and omission of dose demanding projections. Contributions to the possible late effects were estimated on the basis of the organ doses assessed. (author)

  12. Radiation Protection Research: Radiological Assessment

    International Nuclear Information System (INIS)

    Zeevaert, T.

    2000-01-01

    The objectives of SCK-CEN's research in the field of radiological impact assessment are (1) to elaborate and to improve methods and guidelines for the evaluation of restoration options for contaminated sites; (2) to develop, test and improve biosphere models for the performance assessment of radioactive waste disposal in near-surface or geological repositories; (3) to asses the impact of releases from nuclear or industrial installations. Main achievements in these areas for 2000 are summarised

  13. Development of radiological concentrations and unit liter doses for TWRS FSAR radiological consequence calculations

    International Nuclear Information System (INIS)

    Cowley, W.L.

    1996-01-01

    The analysis described in this report develops the Unit Liter Doses for use in the TWRS FSAR. The Unit Liter Doses provide a practical way to calculate conservative radiological consequences for a variety of potential accidents for the tank farms

  14. Patients exposure assessment for radiographic procedures in diagnostic radiology

    International Nuclear Information System (INIS)

    Arandjic, D.; Ciraj-Bjelac, O.; Stankovic, K.; Lazarevic, Dj.; Ciraj-Bjelac, O.)

    2007-01-01

    In this work the results of dose assessment for the most frequent radiographic procedures in diagnostic radiology are shown. Entrance surface doses were assessed for 7 radiographic procedures. Three hospitals, six x-ray units in total, were enrolled in investigation. Patient doses were estimated based on results of x-ray tube output measurements. Finally, doses were compared with Diagnostic reference level. Higher dose values were observed for chest examinations. In comparison with results from other countries, doses from this procedure in Serbia are significantly higher. Estimated doses for other procedures were well below Diagnostic reference levels [sr

  15. Radiological safety and risk assessment

    International Nuclear Information System (INIS)

    Hunter, P.H.; Barg, D.C.; Baird, R.D.; Card, D.H.; de Souza, F.; Elder, J.; Felthauser, K.; Jensen, C.; Winkler, V.

    1982-02-01

    A brief radiological safety and risk assessment of a nuclear power generation center with an adjacent on-site waste disposal facility at a specific site in the State of Utah is presented. The assessment was conducted to assist in determining the feasibility and practicality of developing a nuclear energy center (NEC) in Utah consisting of nine 1250 MWe nuclear pressurized water reactor (PWR) electrical generating units arranged in 3 clusters of 3 units each known as triads. The site selected for this conceptual study is in the Horse Bench area about 15 miles directly south of the town of Green River, Utah. The radiological issues included direct radiation exposures to on-site workers and the off-site population, release of radioactive material, and effects of these releases for both normal operations and accidental occurrences. The basic finding of this study is that the concept of an NEC in the Green River area, specifically at the Horse Bench site, is radiologically feasible

  16. EcoDoses - Improving radiological assessment of doses to man from terrestrial ecosystems. A status report for the NKS-B project 2005

    Energy Technology Data Exchange (ETDEWEB)

    Nielsen, Sven P.; Andersson, Kasper; Thoerring, H. (and others)

    2006-04-15

    Considerable variations in activity concentrations in milk of {sup 137}Cs and {sup 90}Sr were observed between countries or regions due to precipitation patterns, soil types and inhomogeneity of Chernobyl fallout. Time trends indicate that factors influencing ecological half-lives for {sup 90}Sr are not the same as for {sup 137}Cs in the pasturemilk system. Internal doses to Faroese people derive mainly from dairy products, lamb and potatoes. The largest doses were received from nuclear weapons fallout in the early 1960's. {sup 137}Cs causes higher doses than 90Sr, and the regional variability is larger for {sup 137}Cs than for {sup 90}Sr. {sup 137}Cs deposition maps were made of Sweden. Values of 137Cs deposition and precipitation were used in the calculations of Nuclear Weapons Fallout (NWF). The deposition of {sup 137}Cs from the Chernobyl accident was calculated for western Sweden. Lowest levels of NWF {sup 137}Cs deposition density were noted in the north-eastern and eastern Sweden and the highest levels in the western parts. The Chernobyl {sup 137}Cs deposition is highest along the coast and lowest in the south-eastern part and along the middle. The calculated deposition from NWF and Chernobyl in western Sweden was compared to observed deposition and showed good agreement. Ecological halftimes of {sup 137}Cs in perch in Finnish lakes vary by a factor of three. The longest halftime of {sup 137}Cs in perch was 9 y and the shortest 3 y. Norwegian lakes differ from each other with respect to the rates of decrease of {sup 137}Cs in fish. Ecological halftimes of {sup 137}Cs in trout and Arctic char varied from 1 to 5 y. A more rapid reduction of {sup 137}Cs in fish is found in certain Norwegian lakes compared to Finnish lakes. In two Norwegian lakes the 137Cs concentrations in trout remain at about 100 Bq/kg since 1990. The European decision support systems, ARGOS and RODOS, include foodchain modules with default parameters derived from southern Germany. Many

  17. EcoDoses - Improving radiological assessment of doses to man from terrestrial ecosystems. A status report for the NKS-B project 2005

    International Nuclear Information System (INIS)

    Nielsen, Sven P.; Andersson, Kasper; Thoerring, H.

    2006-04-01

    Considerable variations in activity concentrations in milk of 137 Cs and 90 Sr were observed between countries or regions due to precipitation patterns, soil types and inhomogeneity of Chernobyl fallout. Time trends indicate that factors influencing ecological half-lives for 90 Sr are not the same as for 137 Cs in the pasturemilk system. Internal doses to Faroese people derive mainly from dairy products, lamb and potatoes. The largest doses were received from nuclear weapons fallout in the early 1960's. 137 Cs causes higher doses than 90Sr, and the regional variability is larger for 137 Cs than for 90 Sr. 137 Cs deposition maps were made of Sweden. Values of 137Cs deposition and precipitation were used in the calculations of Nuclear Weapons Fallout (NWF). The deposition of 137 Cs from the Chernobyl accident was calculated for western Sweden. Lowest levels of NWF 137 Cs deposition density were noted in the north-eastern and eastern Sweden and the highest levels in the western parts. The Chernobyl 137 Cs deposition is highest along the coast and lowest in the south-eastern part and along the middle. The calculated deposition from NWF and Chernobyl in western Sweden was compared to observed deposition and showed good agreement. Ecological halftimes of 137 Cs in perch in Finnish lakes vary by a factor of three. The longest halftime of 137 Cs in perch was 9 y and the shortest 3 y. Norwegian lakes differ from each other with respect to the rates of decrease of 137 Cs in fish. Ecological halftimes of 137 Cs in trout and Arctic char varied from 1 to 5 y. A more rapid reduction of 137 Cs in fish is found in certain Norwegian lakes compared to Finnish lakes. In two Norwegian lakes the 137Cs concentrations in trout remain at about 100 Bq/kg since 1990. The European decision support systems, ARGOS and RODOS, include foodchain modules with default parameters derived from southern Germany. Many parameters describing foodchain transfer are subject to considerable variation

  18. Personnel radiation dose assessment using a novel dosimeter in the department of radiology and dentistry in a medical facility in Delta State, South-South Nigeria: Our experience in the last 4 years

    OpenAIRE

    Omojola, Akintayo Daniel; Akpochafor, Michael Onoride; Adeneye, Samuel Olaolu; Aniekop, Ukeme Pius; Anizor, Margaret Idongesit; Ekpo, Mary-Ann Etim; Madu, Chibuzor Bede

    2018-01-01

    Objectives. Large percentagesof X-ray facilities in Nigeria do not use radiation monitoring device; a fewpercentage that use them do not evaluate or carryout out assessment programs toascertain the detriment to occupationally exposed workers. This study was aimedat evaluating dose reports from 2013 to 2016 for personnel who operate  radiation facilities and those that workwithin radiation field during certain X-ray procedures/examinations in thedepartment of radiology and dentistry respective...

  19. The Semipalatinsk nuclear test site: a first assessment of the radiological situation and the test-related radiation doses in the surrounding territories.

    Science.gov (United States)

    Gusev, B I; Abylkassimova, Z N; Apsalikov, K N

    1997-09-01

    As a result of atmospheric nuclear tests at the Semipalatinsk test site 'Polygon', adjacent territories were contaminated by radionuclide fallout. The population of some districts in the Semipalatinsk oblast were exposed to elevated levels of radiation. Contamination and exposure mostly resulted from early atmospheric tests. The radiological situation of the Semipalatinsk oblast is described. Effective dose estimates due to external and internal exposure attributable to the 1949 and 1953 tests in villages near the Polygon range from 70 mSv to 4470 mSv.

  20. Nordic Guidance Levels for Patient Doses in Diagnostic Radiology

    International Nuclear Information System (INIS)

    Saxebol, G.; Olerud, H.M.; Hjardemaal, O.; Leitz, W.; Servomaa, A.; Walderhaug, T.

    1998-01-01

    Within the framework of Nordic authoritative cooperation in radiation protection and nuclear safety, recommendations have been prepared dealing with dose constraints in diagnostic radiology. A working group with participants from all the Nordic countries has met and discussed possible implementations of the ICRP dose constraint for medical radiology. Dose constraints, expressed as guidance levels, were specified for six different radiological examinations, i.e. chest, pelvis, lumbar spine, urography, barium meal and enema in units of kerma-area product and entrance surface dose. The recommendations are described in report No 5 in the series 'Report on Nordic Radiation Protection Cooperation'. Examples of dose distributions and factors affecting the patient dose are described in the report. (author)

  1. Radiological Risk Assessment and Survey of Radioactive Contamination for Foodstuffs

    International Nuclear Information System (INIS)

    Lee, W.R.; Lee, C.W.; Choi, K.S.

    2007-11-01

    After the Chernobyl nuclear accident in 1986, a radiological dose assessment and a survey of a radioactive contamination for foodstuffs have been investigated by many countries such as EU, Japan, USA. In the case of Japan which is similar to our country for the imported regions of foodstuffs, there were some instances of the excess for regulation on the maximum permitted levels of radioactive contamination among some imported foodstuffs. Concerns about the radioactive contamination of foodstuffs are increased because of the recently special situation (Nuclear test of North Korea). The purpose of this study is a radiological dose assessment and a survey of a radioactive contamination for foodstuffs in order to reduce the probability of intake of contaminated foodstuffs. Analytical results of the collected samples are below MDA. In this project, the model of radiological dose assessment via the food chain was also developed and radiological dose assessment was conducted based on surveys results of a radioactive contamination for foodstuffs in the Korean open markets since 2002. The results of radiological dose assessment are far below international reference level. It shows that public radiation exposure via food chain is well controlled within the international guide level. However, the radioactive contamination research of imported foodstuffs should be continuous considering the special situation(nuclear test of North Korea). These results are used to manage the radioactive contamination of the imported foodstuffs and also amend the regulation on the maximum permitted levels of radioactive contamination of foodstuffs

  2. Software for the estimation of organ equivalent and effective doses from diagnostic radiology procedures

    International Nuclear Information System (INIS)

    Osei, Ernest K; Barnett, Rob

    2009-01-01

    Diagnostic radiological imaging such as conventional radiography, fluoroscopy and computed tomography (CT) examinations will continue to provide tremendous benefits in modern healthcare. The benefit derived by the patient should far outweigh the risk associated with a properly conducted imaging examination. Nonetheless, it is very important to be able to quantify the risk associated with any radiological examination of patients, and effective dose has been considered a useful indicator of patient exposure. Quantification of the risks associated with radiological imaging is very important as such information will be helpful to physicians and their patients for comparing risks from various imaging examinations and for making informed decisions whenever there is a need for any radiological imaging. The determination of equivalent and effective doses in diagnostic radiology is of interest as a basis for estimates of risk from medical exposures. In this paper we describe a simple computer program OrgDose, which calculates the doses to 27 organs in the body and then calculates the organ equivalent and effective doses and the risk from various procedures in the radiology department including conventional radiography, fluoroscopy and computed tomography examinations. The program will be a useful tool for the medical and paramedical personnel who are involved with assessing organ and effective doses and risks from diagnostic radiology procedures.

  3. SU-E-P-57: Radiation Doses Assessment to Paediatric Patients for Some Digital Diagnostic Radiology Examination in Emergency Department in Qatar

    Energy Technology Data Exchange (ETDEWEB)

    Abdallah, I; Aly, A; Al Naemi, H [Hamad Medical Corporation, Doha (Qatar)

    2015-06-15

    Purpose: The aim of this study was to evaluate radiation doses to pediatric patients undergoing standard radiographic examinations using Direct Digital Radiography (DDR) in Paediatric emergency center of Hamad General Hospital (HGH) in state of Qatar and compared with regional and international Dose Reference Levels (DRLs). Methods: Entrance Skin Dose (ESD) was measured for 2739 patients for two common X-ray examinations namely: Chest AP/PA, Abdomen. Exposure factors such as kV, mAs and Focal to Skin Distance (FSD) were recorded for each patient. Tube Output was measured for a range of selected kV values. ESD for each individual patient was calculated using the tube output and the technical exposure factors for each examination. The ESD values were compared with the some international Dose Reference Levels (DRL) for all types of examinations. Results: The most performed procedure during the time of this study was chest PA/PA (85%). The mean ESD values obtained from AP chest, PA chest and AP abdomen ranged 91–120, 80–84 and 209 – 659 µGy per radiograph for different age’s groups respectively. Two protocols have been used for chest AP and PA using different radiological parameters, and the different of ESD values for chest PA and were 41% for 1 years old child, 57% for 5 years old for chest AP. Conclusion: The mean ESD were compared with those found in literature and were found to be comparable. The radiation dose can be reduced more for Chest AP and PA examination by optimization of each investigation and hence more studies are required for this task. The results presented will serve as a baseline data needed for deriving local reference doses for pediatric X-ray examinations in this local department and hence it can be applied in the whole Qatar.

  4. Radiological assessment of the PET facility

    International Nuclear Information System (INIS)

    Discacciatti, Adrian; Cruzate, Juan A.; Bomben, Ana M.; Carelli, Jorge; Namias, Mario

    2008-01-01

    The radiological assessment of a Positron Emission Tomography (PET) facility consists of the evaluation of the annual effective dose to workers exposed occupationally and to members of the public. This evaluation takes into account the radionuclide involved, the characteristics of the facility, the working procedure and the expected number of patients per year. This paper details the methodology used by the Nuclear Regulatory Authority (in Spanish ARN) to independently assess the design of PET facilities considering only radioprotection aspects. The results of the evaluation are compared with the design requirements established in the ARN regulations to determine whether or not, the facility complies with those requirements, both for workers and for members of the public. As an example of the above mentioned methodology, this paper presents the assessment of a PET facility located in Buenos Aires called Fundacion Centro Diagnostico Nuclear (FCDN). (author)

  5. Fetal dose in radiology, nuclear medicine and radiotherapy; Dosis fetal en radiodiagnostico, medicina nuclear y radioterapia

    Energy Technology Data Exchange (ETDEWEB)

    Rosales, F. J.; Martinez, L. C.; Candela, C.

    2015-07-01

    Sometimes irradiation of the fetus in the mother's womb is inevitable in the field of diagnostic radiology, nuclear medicine and radiotherapy, either through ignorance a priori status of this pregnancy, either because for clinical reasons it is necessary to perform the radiological study or treatment. In the first cases, know the dose at which it has exposed the fetus is essential when assessing the associated risk, while in the second it is when assessing the justification of the test. (Author)

  6. The radiological assessment system for consequence analysis - RASCAL

    International Nuclear Information System (INIS)

    Sjoreen, A.L.; Ramsdell, J.V.; Athey, G.F.

    1996-01-01

    The Radiological Assessment System for Consequence Analysis, Version 2.1 (RASCAL 2.1) has been developed for use during a response to radiological emergencies. The model estimates doses for comparison with U.S. Environmental Protection Agency (EPA) Protective Action Guides (PAGs) and thresholds for acute health effects. RASCAL was designed to be used by U.S. Nuclear Regulatory Commission (NRC) personnel who report to the site of a nuclear accident to conduct an independent evaluation of dose and consequence projections and personnel who conduct training and drills on emergency responses. It allows consideration of the dominant aspects of the source term, transport, dose, and consequences. RASCAL consists of three computational tools: ST-DOSE, FM-DOSE, and DECAY. ST-DOSE computes source term, atmospheric transport, and dose to man from accidental airborne releases of radionuclides. The source-term calculations are appropriate for accidents at U.S. power reactors. FM-DOSE computes doses from environmental concentrations of radionuclides in the air and on the ground. DECAY computes radiological decay and daughter in-growth. RASCAL 2.1 is a DOS application that can be run under Windows 3.1 and 95. RASCAL has been the starting point for other accident consequence models, notably INTERRAS, an international version of RASCAL, and HASCAL, an expansion of RASCAL that will model radiological, biological, and chemical accidents

  7. Analysis of occupational doses in interventional radiology and cardiology installations

    International Nuclear Information System (INIS)

    Vano, E.; Gonzalez, L.; Ten, J.I.; Guibelalde, E.; Fernandez, J.M.

    1997-01-01

    The relationship between patient dose (PD) and occupational dose (OD) is not easily predictable in interventional radiology installations due to a large number of factors which can modify the occupational risk (OR). In the present work an analysis is made of the four main aspects which influence OR, namely, x-ray beam used, radiation protection (RP) tools available (aprons, thyroid protectors, gloves, screens, etc) and their regular use, type and number of procedures performed (diagnostic or therapeutic, complexity level, etc), and RP training level of the specialists. High filtration x-ray beams can entail a decrease of 20% in OD. A regular use of ceiling mounted faceplates can involve dose savings up to 65%. Mean values of dose per procedure for interventional radiologists are something greater (about 15%) than those recorded for cardiologists, except for the dosimeters placed on left forearm and shoulder. The ratio between OD and PD range around 100 μSv/1,000 cGy.cm 2 . The influence of the staff RP training level on OD is difficult to assess. In the IC Service from the Madrid San Carlos University Hospital (SCUH), PD have been reduced in above 30% and OD in a factor of 3, after running some training programmes. (author)

  8. Radiological dose assessment of Department of Energy Pinellas Plant waste proposed for disposal at Laidlaw Environmental Services of South Carolina, Inc

    International Nuclear Information System (INIS)

    Socolof, M.L.; Lee, D.W.

    1996-05-01

    The U.S. Department of Energy (DOE) Pinellas Plant in Largo, FL is proposing to ship and dispose of hazardous sludge, listed as F006 waste, to the Laidlaw Environmental Services of South Carolina, Inc. (Laidlaw) treatment, storage, and disposal facility in Pinewood, South Carolina. This sludge contains radioactive tritium in concentrations of about 28 pCi/g. The objective of this study is to assess the possible radiological impact to workers at the Laidlaw facility and members of the public due to the handling, processing, and burial of the DOE waste containing tritium

  9. Radiological dose assessment of Department of Energy Pinellas Plant waste proposed for disposal at Laidlaw Environmental Services of South Carolina, Inc.

    Energy Technology Data Exchange (ETDEWEB)

    Socolof, M.L.; Lee, D.W.

    1996-05-01

    The U.S. Department of Energy (DOE) Pinellas Plant in Largo, FL is proposing to ship and dispose of hazardous sludge, listed as F006 waste, to the Laidlaw Environmental Services of South Carolina, Inc. (Laidlaw) treatment, storage, and disposal facility in Pinewood, South Carolina. This sludge contains radioactive tritium in concentrations of about 28 pCi/g. The objective of this study is to assess the possible radiological impact to workers at the Laidlaw facility and members of the public due to the handling, processing, and burial of the DOE waste containing tritium.

  10. Radiologic sciences. Faculty needs assessment.

    Science.gov (United States)

    Powers, Kevin J

    2005-01-01

    A total of 326 programs are represented in the data collected. Based on the average number of full- and part-time faculty members reported per program, this survey represents more than 1500 faculty positions. Based on the forecast of retirement and career change for all faculty members, there will be a turnover of 700 to 800 positions over the next 5 to 10 years. Part-time/adjunct faculty vacancies are expected to create the greatest number of opportunities for technologists to make the transition to education, with approximately one third of current part-time/adjunct educators planning on leaving radiologic sciences education within 5 years. To encourage retention of part-time/adjunct educators, annual evaluations should be modified to recognize the important educational role these instructors play. There is a need to create enthusiasm and interest in education as a career pathway for radiologic technologists. Resources are needed that help radiologic technologists make the transition to teaching. Finally, the retention of educators must be emphasized. Program applicant trends indicate radiologic technology students are older, have prior postsecondary education experience or are making a career change. This data emphasizes the need for educators, both full time and part time, to understand the characteristics and needs of the adult learner. Adult learners bring a wealth of education, experience and life skills that create both opportunities and challenges in the classroom and clinical setting. All categories of respondents indicated that their current salaries were greater than those of program graduates in their firstjob. Of interest is that 1 in 5 (20%) of part-time/adjunct educators indicated the opposite--that program graduates earn more in their firstjob than educators earn. When asked about salaries if working full time in clinical practice, the majority of all groups indicated their salary would be about the same or would decrease. Only 20% of program

  11. Genetically significant dose from diagnostic radiology in Great Britain

    Energy Technology Data Exchange (ETDEWEB)

    Darby, S C; Wall, B F [National Radiological Protection Board, Harwell (UK)

    1981-01-01

    A brief discussion is presented of the use of population and child expectancy data to estimate the annual genetically significant dose for diagnostic radiology (GSD). The current estimate of GSD is compared with that reported in a survey 20 years previously. Comparisons are made with estimates of GSD from other countries.

  12. Dose monitoring in radiology departments. Status quo and future perspectives

    International Nuclear Information System (INIS)

    Boos, J.; Bethge, O.T.; Antoch, G.; Kroepil, P.

    2016-01-01

    The number of computed tomography examinations has continuously increased over the last decades and accounts for a major part of the collective radiation dose from medical investigations. For purposes of quality assurance in modern radiology a systematic monitoring and analysis of dose related data from radiological examinations is mandatory. Various ways of collecting dose data are available today, for example the Digital Imaging and Communication in Medicine - Structured Report (DICOM-SR), optical character recognition and DICOM-modality performed procedure steps (MPPS). The DICOM-SR is part of the DICOM-standard and provides the DICOM-Radiation Dose Structured Report, which is an easily applicable and comprehensive solution to collect radiation dose parameters. This standard simplifies the process of data collection and enables comprehensive dose monitoring. Various commercial dose monitoring software devices with varying characteristics are available today. In this article, we discuss legal obligations, various ways to monitor dose data, current dose monitoring software solutions and future perspectives in regard to the EU Council Directive 2013/59/EURATOM.

  13. Organ doses in interventional radiology procedures: Evaluation of software

    International Nuclear Information System (INIS)

    Tort, I.; Ruiz-Cruces, R.; Perez-Martinez, M.; Carrera, F.; Ojeda, C.; Diez de los Rios, A.

    2001-01-01

    Interventional Radiology (IR) procedures require large fluoroscopy times and important number of radiological images, so the levels of radiation to patient are high, which leads us to calculate the organ doses. The objective of this work is to estimate and make a comparison of the results given by the different software that we have to do the calculation of organ doses in complex procedures of IR. To do this, 28 patients have been selected, distributed in the 3 procedures with highest doses. The determination of organ doses and effective doses has been made using the projections utilized and different software based on Monte Carlo Methods: Eff-dose, PCXMC and Diasoft. We have obtained very high dispersion in the average organ dose between the 3 programs. In many cases, it is higher than 25% and in some particular cases, it is greater than 100%. Dispersion obtained in effective doses is not so high, being under 20% in all cases. This shows that a better solution is needed to solve the problem of the organ doses calculation; a more accurate method is necessary that brings us to a trustworthy approach to reality, and, at the moment, that we do not dispose of it. (author)

  14. The patient dose survey and dose reduction in diagnostic radiology

    International Nuclear Information System (INIS)

    Dang Thanh Luong; Duong Van Vinh; Ha Ngoc Thach

    2000-01-01

    This paper presented the results of the patient dose survey in some hospitals in Hanoi from 1995 to 1997. The main investigated types of the X-ray examination were: Chest PA, LAT; Skull PA/AP, LAT; Lumbar spine AP, LAT; and Pelvis AP. The fluctuation of the entrance surface doses (ESD) was too large, even in the same type of X-ray examination and X-ray facility. It was found that the ratio of maximum and minimum ESD were ranged from 1.5 to 18. The mean values of ESD for chest and skull were higher than CEC recommended values, while the mean values of lumbar spine and pelvis were smaller than that of CEC recommended values. The result of dose intercomparison was also reported. Some methods of dose reduction were applied for improving the patient dose in X-ray departments such as a high kV technique, high sensitive screen-film combination. (author)

  15. Radiological characterization and dose assessment in different scenarios of occupational and public exposure to naturally occurring radioactive materials in the Republic of Cuba

    International Nuclear Information System (INIS)

    Fernandez Gomez, Isis Maria

    2012-01-01

    Cuba has identified situations where there working environments with the presence of natural radioactivity. Dose estimates in these environments could exceed the measured values for occupationally exposed workers, without there existed so far, with regulatory requirements for programs of radiation protection. In light of these situations, it has been necessary to assess the potential impact on these working groups of radiational load that they are subjected and establish regulatory criteria for protection in cases that require it. (author) [es

  16. Dose classification scheme for digital imaging techniques in diagnostic radiology

    International Nuclear Information System (INIS)

    Hojreh, A.

    2002-04-01

    Purpose: image quality in diagnostic radiology is determined in crucial extent by the signal-noise-ratio, which is proportional to the applied x-ray dose. Onward technological developments in the diagnostic radiology are therefore frequently connected with a dose increase, which subjectively is hardly or even not perceptible. The aim of this work was to define reproducible standards for image quality as a function of dose and expected therapeutical consequence in case of computed tomography of the paranasal sinuses and the upper and lower jaw (dental CT), whereby practical-clinical purposes are considered. Materials and methods: the image quality of computed tomography of the paranasal sinuses and dental CT was determined by standard deviation of the CT-numbers (pixel noise) in a region of interest of the phantom of American Association of Physicists in Medicine (AAPM phantom) and additionally in the patients CT images. The diagnostic quality of the examination was classified on the basis of patients CT images in three dose levels (low dose, standard dose and high dose). Results: the pixel noise of CT of the paranasal sinuses with soft tissue reconstruction amounts to 19.3 Hounsfield units (HU) for low dose, 8.8 HU for standard dose, and below 8 HU for high dose. The pixel noise of the dental CT with bone (high resolution) reconstruction amounts to 344 HU for low dose, 221 HU for standard dose, and below 200 HU for high dose. Suitable indications for low dose CT are the scanning of body regions with high contrast differences, like the bony delimitations of air-filled spaces of the facial bones, and radiological follow-up examinations with dedicated questions such as axis determination in dental implantology, as well as the images of objects with small diameter such as in case of children. The standard dose CT can be recommended for all cases, in which precise staging of the illness plays an indispensable role for the diagnosis and therapy planning. With high dose

  17. Occupational hand doses in interventional radiology

    International Nuclear Information System (INIS)

    Spasic Jokic, V.; Djurovic, B.; Lukac, S.

    2001-01-01

    In this paper we present the case of a radiologist performing interventional procedures. The radiologist works for number of interventional procedures, but we reported only percutaneous nephrostomy and percutaneous biliary drainage which represent about 30% of his occupational exposure. The radiologist is occupationally exposed for eighteen years and from 1995 has radiation injuries. From 1999, art. hypertension, cataract complicata incip.ou., onychodystrophia and hyperceratosis mani bill. The most important are hands skin injuries. In ordinary dosimetric control low doses less than 10 mGy per year were recorded, so personal dosimetry results and biological results are not in accordance. For that reason we performed additional measurements during many procedures and in this paper we present results for two chosen procedures. Radiation exposure of the radiologist's hands during 200 percutaneous nephrostomy and 63 percutaneous biliary drainage per year are reported. Exposures were measured with thermoluminescent dosemeters (TLD) type CaF 2 :Mn. Hand doses of equivalent of 221 μSv in average per drainage and 31 μSv in average per nephrostomy were recorded. (author)

  18. Dose management in radiology. Review of the technological status

    International Nuclear Information System (INIS)

    Verius, M.

    2015-01-01

    The Euratom directive 2013/59 (''EU directive for radiation protection'') has to be implemented into national law by spring 2018 and requires a complete recording of patient dosages and relevant parameters. Additionally, a medical physics expert has to be consulted for each radiological examination above a defined threshold. A complete recording of the dosage administered from all modalities and optimization of the radiological procedures should result in a reduction of the total dosage. This can be achieved by automated systems that incorporate not only the detection of the dose parameters but also the evaluation and analysis of these data. When provided with warning levels such a system should be able to inform or warn the operator when dose thresholds have been exceeded or even better inform the operator about possible excess dosages before an examination. Depending on the information provided by the modality, dose management systems can operate at different levels in the picture archiving and communication system (PACS), radiological and hospital information systems (RIS/HIS) or with the header information of a digital imaging and communications in medicine (DICOM) image and evaluate and analyze this data. A practicable use of such systems is only possible by close cooperation of medical personnel, medical physicists and information technology (IT) administrators. Various systems are available commercially or free but an individual adaptation of these systems is useful and necessary, depending on the requirements of the radiology practice or hospital. (orig.) [de

  19. Preliminary characterization of dose in personnel of interventional radiology

    International Nuclear Information System (INIS)

    Godolfim, Laura Larre; Anes, Mauricio; Bacelar, Alexandre; Lykawka, Rochelle

    2016-01-01

    Exposure to X-rays of Interventional Radiology professionals (IR) impacts in the high dose rate received by these individuals, and there are reports of biological effects of this professional activity. Therefore, it is fomented greater control over the doses received by these workers. This research intends to characterize the doses received by the professionals during IR procedures. We evaluated the doses of radiologists, anesthesiologists and nursing staff of the Hospital de Clinicas de Porto Alegre, through measures with dosimeters of the OSL type, distributed in up to six regions of the body of these professionals. Until now were accompanied 33 cholangiography procedures and 29 embolization procedures. As a preliminary result, it was possible to identify a wide variation between doses of the professionals of the same function in each procedure. In overview, the dose of the professionals presented in descending order as a radiologist 1> radiologist 2 > anesthetist > nursing. (author)

  20. Systems automated reporting of patient dose in digital radiology

    International Nuclear Information System (INIS)

    Collado Chamorro, P.; Sanz Freire, C. J.; Martinez Mirallas, O.; Tejada San Juan, S.; Lopez de Gammarra, M. S.

    2013-01-01

    It has developed a procedure automated reporting of doses to patients in Radiology. This procedure allows to save the time required of the data used to calculate the dose to patients by yields. Also saves the time spent in the transcription of these data for the realization of the necessary calculations. This system has been developed using open source software. The characteristics of the systems of digital radiography for the automation of procedures, in particular the registration of dose should benefit from patient. This procedure is validated and currently in use at our institution. (Author)

  1. Discussion on the method of environmental radiological impact assessment for the highway construction project

    International Nuclear Information System (INIS)

    Qiu Guohua

    2008-01-01

    Based on the characteristics and environmental radiological impact of the highway construction project, the basic procedure of environmental radiological impact assessment for the highway construction project is put forward, including analysis and determination of contamination sources, selection of evaluation factors, determination of assessment range and dose limit, environmental investigation, environmental impact prediction and assessment. The working method of each procedure is analyzed. (authors)

  2. Optimization of radiological protection and dose constraints in the new draft ICRP Recommendations 2006

    International Nuclear Information System (INIS)

    Klener, V.

    2007-01-01

    The overall concept of the new ICRP Recommendations 2006 is analyzed, the concept of dose constraints as a basic tool of radiological protection management is described, arguments and criticisms against the current proposal are cited and points of dispute highlighted, and perspectives of the Recommendations are assessed. (author)

  3. Development of mobile radiological assessment laboratory

    International Nuclear Information System (INIS)

    Pujari, R.N.; Saindane, Shashank S.; Jain, Amit; Parmar, Jayesh; Narsaiah, M.V.R.; Pote, M.B.; Murali, S.; Chaudhury, Probal

    2018-01-01

    During any emergency situations real-time radiation measurements and the fast analysis of the measured radiological data are of crucial importance. The newly developed mobile vehicle based laboratory known as 'Radiological Assessment Laboratory' (RAL) can be used for real time measurements in different radiation emergency scenarios, such as the release of radioactive materials from a radiological/nuclear incident, during search of an orphan source or during radioisotope transportation. RAL is equipped with several high sensitive detectors/systems such as NaI(Tl) gamma spectrometers, large size plastic scintillators and air-sampler, along with GPS and data transfer capability through GSM modem

  4. Radiological dose reconstruction for birds reconciles outcomes of Fukushima with knowledge of dose-effect relationships

    DEFF Research Database (Denmark)

    Garnier-Laplace, Jacqueline; Beaugelin-Seiller, Karine; Della-Vedova, Claire

    2015-01-01

    We reconstructed the radiological dose for birds observed at 300 census sites in the 50-km northwest area affected by the accident at the Fukushima Daiichi nuclear power plant over 2011-2014. Substituting the ambient dose rate measured at the census points (from 0.16 to 31 μGy h(-1)) with the dos...

  5. Radiological risk assessment for radioactive contamination at landfill site

    International Nuclear Information System (INIS)

    Devgun, J.S.

    1990-01-01

    A limited-scope preliminary assessment of radiological risk has been conducted for a landfill site where radioactive residues resulting from past uranium ore processing operations are present. Potential radiation doses to an individual under different scenarios have been predicted using the RESRAD computer code. The assessment provides useful input to the remedial action planning for the site that is currently underway. 7 refs., 6 figs., 3 tabs

  6. ICRP recommendations on 'managing patient dose in digital radiology'

    International Nuclear Information System (INIS)

    Vano, E.

    2005-01-01

    The International Commission on Radiological Protection (ICRP) approved the publication of a document on 'Managing patient dose in digital radiology' in 2003. The paper describes the content of the report and some of its key points, together with the formal recommendations of the Commission on this topic. With digital techniques exists not only the potential to improve the practice of radiology but also the risk to overuse radiation. The main advantages of digital imaging: wide dynamic range, post-processing, multiple viewing options, electronic transfer and archiving possibilities are clear but overexposures can occur without an adverse impact on image quality. It is expected that the ICRP report helps to profit from the benefits of this important technological advance in medical imaging with the best management of radiation doses to the patients. It is also expected to promote training actions before the digital techniques are introduced in the radiology departments and to foster the industry to offer enough technical and dosimetric information to radiologists, radiographers and medical physicists to help in the optimisation of the imaging. (authors)

  7. Doses to patients from dental radiology in France

    International Nuclear Information System (INIS)

    Benedittini, M.; Maccia, C.; Lefaure, C.; Fagnani, F.

    1989-01-01

    In France, a national study was undertaken to estimate both dental radiology practices (equipment and activity) and the associated population collective dose. This study was done in two steps: A nationwide survey was conducted on the practitioner categories involved in dental radiology, and dosimetric measurements were performed on patients and on an anthropomorphic phantom by using conventional dental x-ray machines and pantomographic units. A total of 27.5 x 10(6) films were estimated to have been performed in 1984; 6% of them were pantomographic and 94% were conventional. Most of the organ doses measured for one intra-oral film were lower than 1 mGy (100 mrad); pantomogram dose values were generally higher than intra-oral ones. The collective effective dose equivalent figure was 2,000 person-Sv (2 x 10(5) person rem) leading to a per head dose equivalent of 0.037 mSv (3.7 mrem). The study allowed authors to identify ways to reduce the patient dose in France (e.g., implementing the use of long cone devices and controlling darkroom practices)

  8. Dose Evaluation and Quality Criteria in Dental Radiology

    International Nuclear Information System (INIS)

    Gori, C.; Rossi, F.; Stecco, A.; Villari, N.; Zatelli, G.

    2000-01-01

    Radioprotection in dental radiology is of particular interest in the framework of the Revised Medical Exposure Directive for the great number of examinations involving the adult as well as the paediatric population (Article 9: Special Practice). The present study is intended to find the quality criteria of orthodontic imaging and for evaluating the dose absorbed within the dental and maxillary volume in connection with radiological examinations performed with either spiral CT, dental panoramic tomography or teleradiography. The X ray dose to organs sited in the body, neck, ocular and intracranial area was measured using lithium fluoride dosemeters, positioned in a Rando phantom. Quality criteria have been established by an expert radiologist considering the diagnostic information obtained in the images. The dosimetric data obtained were comparable with other authors', although with some differences due to technical characteristics. These result data are useful for choosing the patient's diagnostic path, considering the radiobiological risk associated with increasing orthodontic imaging. (author)

  9. Radiological assessment of the Esk Estuary

    International Nuclear Information System (INIS)

    Howorth, J.M.; Barr, H.M.; Toole, J.; Strange, L.P.

    1993-01-01

    An assessment has been carried out of the radiological impact of artificial radionuclides in the Esk estuary in Cumbria, UK. Measurements were made of the distributions of 137 Cs, 239 + 240 Pu, and 241 Am in water, surface bed sediments and core profiles. The highest measured concentrations in surface sediments were 2.8 Bq g -1 of 137 Cs, 3.1 Bq g -1 of 239 + 240 Pu and 4.7 Bq g -1 of 241 Am. These values represent significant decreases from similar measurements made in 1970-1980. The measured behaviour of the actinides in low salinity water at the head of the estuary supports previous observations of actinide remobilisation from the bed. A model has been developed which simulates the long-term behaviour of radioactivity in the estuary. The model incorporates representations of tidal mixing, sediment transport, seasonal and long-term sediment accretion. The model also represents long-term build-up in salt marsh regions. The model gives good agreement with measured distributions of 137 Cs, but tends to underestimate actinide concentrations by factors of 2-3. Dose calculations show the importance of radionuclide uptake through livestock grazing sea-washed pasture alongside the estuary. 137 Cs and 241 Am are identified as the most important radionuclides considered in the assessment. (Author)

  10. Radiological impact assessment of building materials on ordinary houses dwellers

    International Nuclear Information System (INIS)

    Campos, M.P. de.

    1994-01-01

    The radiological impact due to building materials on habitants living in the Santo Andre district of Sao Paulo state, Brazil, was assessed through the total effective dose equivalent rate determination, for external and internal irradiation. The effective dose equivalent rate for external irradiation was calculated by the gamma spectrometry determination of natural radionuclides specific activity in the dwelling materials. The effective dose equivalent rate due to 222 Rn inhalation was calculated through the radon indoor activity determination by using solid state nuclear track detectors. (author). 46 refs, 6 figs, 14 tabs

  11. Assessment of internal doses

    CERN Document Server

    Rahola, T; Falk, R; Isaksson, M; Skuterud, L

    2002-01-01

    There is a definite need for training in dose calculation. Our first course was successful and was followed by a second, both courses were fully booked. An example of new tools for software products for bioassay analysis and internal dose assessment is the Integrated Modules for Bioassay Analysis (IMBA) were demonstrated at the second course. This suite of quality assured code modules have been adopted in the UK as the standard for regulatory assessment purposes. The intercomparison measurements are an important part of the Quality Assurance work. In what is known as the sup O utside workers ' directive it is stated that the internal dose measurements shall be included in the European Unions supervision system for radiation protection. The emergency preparedness regarding internal contamination was much improved by the training with and calibration of handheld instruments from participants' laboratories. More improvement will be gained with the handbook giving practical instructions on what to do in case of e...

  12. Assessment of the radiation risk from diagnostic radiology

    International Nuclear Information System (INIS)

    Streffer, C.; Mueller, W.U.

    1995-01-01

    In any assessment of radiation risks from diagnostic radiology the main concern is the possible induction of cancer. It now appears to be beyond all doubt that ionizing rays invite the development of cancer in humans. The radiation doses encountered in diagnostic radiology generally vary from 1 to 50 mSv. For this dose range, no measured values are available to ascertain cancer risks from ionizing rays. The effects of such doses must therefore be extrapolated from higher dose levels under consideration of given dose-effect relationships. All relevant figures for diagnostic X-ray measures are therefore mathematically determined approximate values. The stochastic radiation risk following non-homogeneous radiation exposure is assessed on the basis of the effective dose. This dose was originally introduced to ascertain the risk from radioactive substances incorporated at the working place. A secondary intention was to trigger further developmental processes in radiation protection. Due to the difficulties previously outlined and the uncertainties surrounding the determination and assessment of the effective dose from diagnostic X-ray procedures, this dose should merely be used for technological refinements and comaprisons of examination procedures. It appears unreasonable that the effective doses determined for the individual examinations are summed up to obtain a collective effective dose and to multiply this with a risk factor so as to give an approximation of the resulting deaths from cancer. A reasonable alternative is to inform patients subjected to X-ray examinations about the associated radiation dose and to estimate form this the magnitude of the probable radiation risk. (orig./MG) [de

  13. Estimate of dose in interventional radiology: a study of cases

    International Nuclear Information System (INIS)

    Pinto, N.; Braz, D.; Lopes, R.; Vallim, M.; Padilha, L.; Azevedo, F.; Barroso, R.

    2006-01-01

    Values of absorbed dose taken by patients and professionals involved in interventional radiology can be significant mainly for the reason of these proceedings taking long time of fluoroscopy There are many methods to estimate and reduce doses of radiation in the interventional radiology, particularly because the fluoroscopy is responsible for the high dose contribution in the patient and in the professional. The aim of this work is the thermoluminescent dosimetry to estimate the dose values of the extremities of the professionals involved in the interventional radiology and the product dose-area was investigated using a Diamentor. This evaluation is particularly useful for proceedings that interest multiple parts of the organism. In this study were used thermoluminescent dosimeters (LiF:Mg, Ti - Harshaw) to estimate the dose values of the extremities of the professionals and to calibrate them. They were irradiated with X rays at 50 mGy, in Kerma in air and read in the reader Harshaw-5500. The product dose-area (D.A.P.) were obtained through the Diamentor (M2-P.T.W.) calibrated in Cgy.cm 2 fixed in the exit of the X-rays tube. The patients of these study were divided in three groups: individuals submitted to proceedings of embolization, individuals submitted to cerebral and renal arteriography and individuals submitted to proceedings of Transjungular Inthahepatic Porta Systemic Stent Shunt (TIPS). The texts were always carried out by the same group: radiologist doctor), an auxiliary doctor and a nursing auxiliary. The section of interventional radiology has an Angiostar Plus Siemens equipment type arc C, in which there is trifocal Megalix X-ray tube and a intensifier of image from Sirecon 40-4 HDR/33 HDR. In this work the dose estimated values were 137.25 mSv/year for the doctors, 40.27 mSv/year for the nursing and 51.95 mSv/year for the auxiliary doctor and they are below the rule, but in this study it was not taken in consideration the emergency texts as they were

  14. Optimization of the quality and dose in thorax general radiology

    International Nuclear Information System (INIS)

    Hwang, Suy Ferreira

    2001-01-01

    Image quality and radiation dose at skin entrance in chest radiography were studied for three exposure protocols, denoted as 1, 2 and 3. Protocol 1 represents the most used technique in radiology services in our country. This technique consists of the following parameters: 81 kV tube voltage, anti-scatter grid and 2 m focus-film distance. Protocol 2 uses the same parameters of the Protocol 1, without grid. Protocol 3 uses I 33kV without grid and 3,5 m focus-film distance. In Protocols 2 and 3 a 30 em air gap was used between patient and film. Two samples of 50 patients were radiographed in two different facilities, herein denoted 1 and 2. Protocol 1 was used in facility I to radiograph the first patient sample, and Protocols 2 and 3 were used in facility 2 to radiograph the second patient sample. Three experts in chest radiology evaluated the obtained chest images according anatomical quality criteria for this examination. For each patient exposure the radiation dose at skin entrance was measured. In this work, a chest phantom, containing test objects to evaluate quantitatively image quality, was made. The phantom was radiographed with the three protocols herein investigated. Results of this study showed clearly that Protocol 3 presents an average dose at skin entrance about half than Protocol 2 and about one third of Protocol 1. In regard to chest radiographic images and radiation dose, it was statistically demonstrated that the Protocol 3 is better than Protocols 1 and 2, with the improvement of the image quality and patient dose reduction in order of 3 times. This work also discusses the perspective of using optimized exposure technique proposed by Protocol 3 as an alternative technique far chest radiographic examinations to those currently used in our diagnostic radiology facilities. (author)

  15. Collective dose estimation in Portuguese population due to medical exams of diagnostic radiology and nuclear medicine

    International Nuclear Information System (INIS)

    Teles, Pedro; Vaz, Pedro; Paulo, Graciano; Santos, Joana; Pascoal, Ana; Lanca, Isabel; Matela, Nuno; Sousa, Patrick; Carvoeiras, Pedro; Parafita, Rui; Simaozinho, Paula

    2013-01-01

    In order to assess the exposure of the Portuguese population to ionizing radiation due to medical examinations of diagnostic radiology and nuclear medicine, a working group, consisting of 40 institutions, public and private, was created to evaluation the coletive dose in the Portuguese population in 2010. This work was conducted in collaboration with the Dose Datamed European consortium, which aims to assess the exposure of the European population to ionizing radiation due to 20 diagnostic radiology examinations most frequent in Europe (the 'TOP 20') and nuclear medicine examinations. We obtained an average value of collective dose of ≈ 1 mSv/caput, which puts Portugal in the category of countries medium to high exposure to Europe. We hope that this work can be a starting point to bridge the persistent lack of studies in the areas referred to in Portugal, and to enable the characterization periodic exposure of the Portuguese population to ionizing radiation in the context of medical applications

  16. Methods of determining the effective dose in dental radiology

    International Nuclear Information System (INIS)

    Thilander-Klang, A.; Helmrot, E.

    2010-01-01

    A wide variety of X-ray equipment is used today in dental radiology, including intra-oral, ortho-pan-tomographic, cephalo-metric, cone-beam computed tomography (CBCT) and computed tomography (CT). This raises the question of how the radiation risks resulting from different kinds of examinations should be compared. The risk to the patient is usually expressed in terms of effective dose. However, it is difficult to determine its reliability, and it is difficult to make comparisons, especially when different modalities are used. The classification of the new CBCT units is also problematic as they are sometimes classified as CT units. This will lead to problems in choosing the best dosimetric method, especially when the examination geometry resembles more on an ordinary ortho-pan-tomographic examination, as the axis of rotation is not at the centre of the patient, and small radiation field sizes are used. The purpose of this study was to present different methods for the estimation of the effective dose from the equipment currently used in dental radiology, and to discuss their limitations. The methods are compared based on commonly used measurable and computable dose quantities, and their reliability in the estimation of the effective dose. (authors)

  17. Radiological impact assessment around Kudankulam

    International Nuclear Information System (INIS)

    Vijayakumar, B.; Thomas, G.; Jayasudha, P.; Selvi, B.S.; Preetha, B.; Ravi, P.M.

    2017-01-01

    Two light water reactors, VVER in Russian, have been constructed at Kudankulam near the south eastern tip of India. The reactors belong to the family of Pressurized Water Reactors (PWR), which is the predominant type in operation, the world over. A systematic pre operational study has been conducted around the Kudankulam site for about 10 years and the external dose due to natural sources of radiation exposure have been established. The first unit of Kudankulam became critical in the year July 2013. Following plant operation, the gaseous and liquid effluent releases from the plant have been characterized and dose to members of the public due to plant operation has been computed for two full years 2014 and 2015. The public dose due to plant operation has been estimated to be less than 0.003 % of applicable ICRP/AERB dose limit. The background external radiation exposure during the period of plant operation has remained essentially the same as observed during plant pre operational phase. (author)

  18. Radiological risk assessment of environmental radon

    Energy Technology Data Exchange (ETDEWEB)

    Khalid, Norafatin; Majid, Amran Ab; Yahaya, Redzuwan; Yasir, Muhammad Samudi [Nuclear Science Programme, School of Applied Physics, Faculty of Science and Technology, Universiti Kebangsaan Malaysia, 43600 Bangi, Selangor Darul Ehsan (Malaysia)

    2013-11-27

    Measurements of radon gas ({sup 222}Rn) in the environmental are important to assess indoor air quality and to study the potential risk to human health. Generally known that exposure to radon is considered the second leading cause of lung cancer after smoking. The environmental radon concentration depends on the {sup 226}Ra concentration, indoor atmosphere, cracking on rocks and building materials. This study was carried out to determine the indoor radon concentration from selected samples of tin tailings (amang) and building materials in an airtight sealed homemade radon chamber. The radiological risk assessment for radon gas was also calculated based on the annual exposure dose, effective dose equivalent, radon exhalation rates and fatal cancer risk. The continuous radon monitor Sun Nuclear model 1029 was used to measure the radon concentration emanates from selected samples for 96 hours. Five types of tin tailings collected from Kampar, Perak and four samples of building materials commonly used in Malaysia dwellings or building constructions were analysed for radon concentration. The indoor radon concentration determined in ilmenite, monazite, struverite, xenotime and zircon samples varies from 219.6 ± 76.8 Bq m{sup −3} to 571.1 ± 251.4 Bq m{sup −3}, 101.0 ± 41.0 Bq m{sup −3} to 245.3 ± 100.2 Bq m{sup −3}, 53.1 ± 7.5 Bq m{sup −3} to 181.8 ± 9.7 Bq m{sup −3}, 256.1 ± 59.3 Bq m{sup −3} to 652.2 ± 222.2 Bq m{sup −3} and 164.5 ± 75.9 Bq m{sup −3} to 653.3 ± 240.0 Bq m{sup −3}, respectively. Whereas, in the building materials, the radon concentration from cement brick, red-clay brick, gravel aggregate and cement showed 396.3 ± 194.3 Bq m{sup −3}, 192.1 ± 75.4 Bq m{sup −3}, 176.1 ± 85.9 Bq m{sup −3} and 28.4 ± 5.7 Bq m{sup −3}, respectively. The radon concentration in tin tailings and building materials were found to be much higher in xenotime and cement brick samples than others. All samples in tin tailings were exceeded the

  19. Optimization of Patient Doses in Interventional Radiology and Cardiology

    International Nuclear Information System (INIS)

    Nikodemova, D.; Boehm, K.

    2011-01-01

    Interventional radiology and cardiology belongs to the imaging modalities connected with significantly higher radiation exposure of patients and medical staff, compared to the exposure during other diagnostic procedures. The objective of this presentation is to promote typical technical parameters and parameters related to the radiation policy, used during the most frequent endovascular and cardiology procedures, as well as the monitoring of the exposure of patients. The presented study reports the results of collecting the data of monitoring doses received by 318 patients undergoing interventional examinations in 3 various departments of the Slovak National Institute of Cardiology and Vascular Diseases. There were 9 different endovascular and cardiology procedures reviewed. The reported patient's radiation exposures were established by using the KAP values, directly shown on the display of the X-ray equipment. From the measured KAP values the entrance surface doses were calculated. Equivalent doses have been measured on hands, legs and other parts of medical staff body, by using electronic dosimeters or thermoluminescent dosimeters. The presented results have covered a wide range of the measured fluoroscopy time values, different number of acquisitions used in various interventional procedures, various cumulated KAP values and also a wide range of the cumulated entrance surface doses. The occupational doses of the operators, followed during dose measurements on their left hands, covered the range from 0.1 μSv to 1513 μSv for one examination performed. The important contribution of the presented results to the radiation protection policy in the Slovak Republic is the mapping of the current situation of the radiation exposure of patients undergoing the chosen interventional examinations and the professional radiation exposure level of interventional operators, providing the most significant interventional procedures in the Slovak interventional hospitals. The

  20. Federal Radiological Monitoring and Assessment Center. The analytical response

    International Nuclear Information System (INIS)

    Nielsen, E.C.

    2005-01-01

    The Federal Radiological Monitoring and Assessment Center (FRMAC) is authorized by the Federal Radiological Emergency Response Plan to coordinate all off-site radiological response assistance to state and local governments, in the event of a major radiological emergency in the United States. The FRMAC is established by the U.S. Department of Energy, National Nuclear Security Administration, to coordinate all Federal assets involved in conducting a comprehensive program of radiological environmental monitoring, sampling, radioanalysis, quality assurance, and dose assessment. During an emergency response, the initial analytical data is provided by portable field instrumentation. As incident responders scale up their response based on the seriousness of the incident, local analytical assets and mobile laboratories add additional capability and capacity. During the intermediate phase of the response, data quality objectives and measurement quality objectives are more rigorous. These higher objectives will require the use of larger laboratories, with greater capacity and enhanced capabilities. These labs may be geographically distant from the incident, which will increase sample management challenges. Emergency radioanalytical capability and capacity and its utilization during FRMAC operations are discussed. (author)

  1. Federal Radiological Monitoring and Assessment Center Analytical Response

    International Nuclear Information System (INIS)

    Nielsen, E.C.

    2003-01-01

    The Federal Radiological Monitoring and Assessment Center (FR-MAC) is authorized by the Federal Radiological Emergency Response Plan to coordinate all off-site radiological response assistance to state and local government s, in the event of a major radiological emergency in the United States. The FR-MAC is established by the U.S. Department of Energy, National Nuclear Security Administration, to coordinate all Federal assets involved in conducting a comprehensive program of radiological environmental monitoring, sampling, radioanalysis, quality assurance, and dose assessment. During an emergency response, the initial analytical data is provided by portable field instrumentation. As incident responders scale up their response based on the seriousness of the incident, local analytical assets and mobile laboratories add additional capability and capacity. During the intermediate phase of the response, data quality objectives and measurement quality objectives are more rigorous. These higher objectives will require the use of larger laboratories, with greater capacity and enhanced capabilities. These labs may be geographically distant FR-om the incident, which will increase sample management challenges. This paper addresses emergency radioanalytical capability and capacity and its utilization during FR-MAC operations

  2. Radiation exposure and dose evaluation in intraoral dental radiology

    International Nuclear Information System (INIS)

    Poppe, B.; Looe, H. K.; Pfaffenberger, A.; Eenboom, F.; Chofor, N.; Sering, M.; Ruehmann, A.; Poplawski, A.; Willborn, K.

    2007-01-01

    In this study, dose area product measurements have been performed to propose diagnostic reference levels (DRLs) in intraoral dental radiology. Measurements were carried out at 60 X-ray units for all types of intraoral examinations performed in clinical routine. The third quartile values calculated range from 26.2 to 87.0 mGy cm 2 . The results showed that there exists a large difference between the patient exposures among different dental facilities. It was also observed that dentists working with faster film type or higher tube voltage are not always associated with lower exposure. The study demonstrated the necessity to have the DRLs laid out as guidelines in dental radiology. (authors)

  3. [Optimization of radiological scoliosis assessment].

    Science.gov (United States)

    Enríquez, Goya; Piqueras, Joaquim; Catalá, Ana; Oliva, Glòria; Ruiz, Agustí; Ribas, Montserrat; Duran, Carmina; Rodrigo, Carlos; Rodríguez, Eugenia; Garriga, Victoria; Maristany, Teresa; García-Fontecha, César; Baños, Joan; Muchart, Jordi; Alava, Fernando

    2014-07-01

    Most scoliosis are idiopathic (80%) and occur more frequently in adolescent girls. Plain radiography is the imaging method of choice, both for the initial study and follow-up studies but has the disadvantage of using ionizing radiation. The breasts are exposed to x-ray along these repeated examinations. The authors present a range of recommendations in order to optimize radiographic exam technique for both conventional and digital x-ray settings to prevent unnecessary patients' radiation exposure and to reduce the risk of breast cancer in patients with scoliosis. With analogue systems, leaded breast protectors should always be used, and with any radiographic equipment, analog or digital radiography, the examination should be performed in postero-anterior projection and optimized low-dose techniques. The ALARA (as low as reasonable achievable) rule should always be followed to achieve diagnostic quality images with the lowest feasible dose. Copyright © 2014. Published by Elsevier Espana.

  4. Dose. Detriment. Limit assessment

    International Nuclear Information System (INIS)

    Breckow, J.

    2015-01-01

    One goal of radiation protection is the limitation of stochastic effects due to radiation exposure. The probability of occurrence of a radiation induced stochastic effect, however, is only one of several other parameters which determine the radiation detriment. Though the ICRP-concept of detriment is a quantitative definition, the kind of detriment weighting includes somewhat subjective elements. In this sense, the detriment-concept of ICRP represents already at the stage of effective dose a kind of assessment. Thus, by comparing radiation protection standards and concepts interconvertible or with those of environment or occupational protection one should be aware of the possibly different principles of detriment assessment.

  5. Fast skin dose estimation system for interventional radiology.

    Science.gov (United States)

    Takata, Takeshi; Kotoku, Jun'ichi; Maejima, Hideyuki; Kumagai, Shinobu; Arai, Norikazu; Kobayashi, Takenori; Shiraishi, Kenshiro; Yamamoto, Masayoshi; Kondo, Hiroshi; Furui, Shigeru

    2018-03-01

    To minimise the radiation dermatitis related to interventional radiology (IR), rapid and accurate dose estimation has been sought for all procedures. We propose a technique for estimating the patient skin dose rapidly and accurately using Monte Carlo (MC) simulation with a graphical processing unit (GPU, GTX 1080; Nvidia Corp.). The skin dose distribution is simulated based on an individual patient's computed tomography (CT) dataset for fluoroscopic conditions after the CT dataset has been segmented into air, water and bone based on pixel values. The skin is assumed to be one layer at the outer surface of the body. Fluoroscopic conditions are obtained from a log file of a fluoroscopic examination. Estimating the absorbed skin dose distribution requires calibration of the dose simulated by our system. For this purpose, a linear function was used to approximate the relation between the simulated dose and the measured dose using radiophotoluminescence (RPL) glass dosimeters in a water-equivalent phantom. Differences of maximum skin dose between our system and the Particle and Heavy Ion Transport code System (PHITS) were as high as 6.1%. The relative statistical error (2 σ) for the simulated dose obtained using our system was ≤3.5%. Using a GPU, the simulation on the chest CT dataset aiming at the heart was within 3.49 s on average: the GPU is 122 times faster than a CPU (Core i7-7700K; Intel Corp.). Our system (using the GPU, the log file, and the CT dataset) estimated the skin dose more rapidly and more accurately than conventional methods.

  6. Analyses of superficial and depth doses in intraoral radiology

    Energy Technology Data Exchange (ETDEWEB)

    Silva Santos de Oliveira, C.; Morais, R.P. de; Nascimento Souza, D. do [Universidade Federal de Sergipe - CCET - Dept. de Fisica, Sao Cristovao, SE (Brazil)

    2006-07-01

    In this work dosimetric analysis using thermoluminescence technique to study the beams characteristics of x-rays employed in dental radiology has been carried out. The obtained results with CaSO{sub 4}:Dy thermoluminescent dosimeters (TLD) were compared to the doses obtained with parallel-plates ionization chamber. Dosimetric evaluations were also done using radiographic films of large dimensions. The x-rays equipments analyzed were installed in the radiological services of Odontology Department of Sergipe Federal University (U.F.S.). Depending on the anatomical region to be examined the proper exposure time was select, for a fix voltage of 70 kV. The results with TLD and ionization chamber have been determined to female and male individuals. The intraoral regions analysed were the peri apical of the incisors, molar and pre-molar teeth and the occlusive region. These regions were simulated using acrylic plates absorbers installed on the film packet holder. The evaluation of the depth doses in the intraoral tissue was obtained using different acrylic plate thickness. The air kerma values have been evaluated with the ionization chamber located in the dental cone exit of the x-rays equipments. The integrated areas of the thermoluminescent glow curves showed coherent values when compared to the ones obtained with the ionization chamber and both methods presented a linear dependence with the exposition time. The analyses with films have allowed the evaluation of the beam scattering in the simulator apparatus. The studies had proven that the analysis of superficial dose and in depth used in dental radiology can be carried with thermoluminescent dosimeters. (authors)

  7. Analyses of superficial and depth doses in intraoral radiology

    International Nuclear Information System (INIS)

    Silva Santos de Oliveira, C.; Morais, R.P. de; Nascimento Souza, D. do

    2006-01-01

    In this work dosimetric analysis using thermoluminescence technique to study the beams characteristics of x-rays employed in dental radiology has been carried out. The obtained results with CaSO 4 :Dy thermoluminescent dosimeters (TLD) were compared to the doses obtained with parallel-plates ionization chamber. Dosimetric evaluations were also done using radiographic films of large dimensions. The x-rays equipments analyzed were installed in the radiological services of Odontology Department of Sergipe Federal University (U.F.S.). Depending on the anatomical region to be examined the proper exposure time was select, for a fix voltage of 70 kV. The results with TLD and ionization chamber have been determined to female and male individuals. The intraoral regions analysed were the peri apical of the incisors, molar and pre-molar teeth and the occlusive region. These regions were simulated using acrylic plates absorbers installed on the film packet holder. The evaluation of the depth doses in the intraoral tissue was obtained using different acrylic plate thickness. The air kerma values have been evaluated with the ionization chamber located in the dental cone exit of the x-rays equipments. The integrated areas of the thermoluminescent glow curves showed coherent values when compared to the ones obtained with the ionization chamber and both methods presented a linear dependence with the exposition time. The analyses with films have allowed the evaluation of the beam scattering in the simulator apparatus. The studies had proven that the analysis of superficial dose and in depth used in dental radiology can be carried with thermoluminescent dosimeters. (authors)

  8. Determination of organ doses in radiographic imaging and diagnostic radiology

    International Nuclear Information System (INIS)

    Rathjen, M.

    1981-01-01

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

  9. Evaluation of patient radiation doses using DAP meter in interventional radiology procedures

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Byung Sam [Dept. of Radiological Technology. Shingu University, Sungnam (Korea, Republic of); Yoon, Yong Su [Dept. of Health Sciences, Graduate School of Medical Sciences, Kyushu Univeristy, Kyushu (Japan)

    2017-03-15

    The author investigated interventional radiology patient doses in several other countries, assessed accuracy of DAP meters embedded in intervention equipment in domestic country, conducted measurement of patient doses for 13 major interventional procedures with use of Dose Area Product(DAP) meters from 23 hospitals in Korea, and referred to 8,415 cases of domestic data related to interventional procedures by radiation exposure after evaluation the actual effective of dose reduction variables through phantom test. Finally, dose reference level for major interventional procedures was suggested. In this study, guidelines for patient doses were 237.7 Gy·cm{sup 2} in TACE, 17.3 Gy·cm{sup 2} in AVF, 114.1 Gy·cm{sup 2} in LE PTA and STENT, 188.5 Gy·cm{sup 2} in TFCA, 383.5 Gy·cm{sup 2} in Aneurysm Coil, 64.6 Gy·cm{sup 2} in PTBD, 64.6 Gy·cm{sup 2} in Biliary Stent, 22.4 Gy·cm{sup 2} in PCN, 4.3 Gy·cm{sup 2} in Hickman, 2.8 Gy·cm{sup 2} in Chemo-port, 4.4 Gy·cm{sup 2} in Perm-Cather, 17.1 Gy·cm{sup 2} in PCD, and 357.9 Gy·cm{sup 2} in Vis, EMB. Dose reference level acquired in this study is considered to be able to use as minimal guidelines for reducing patient dose in the interventional radiology procedures. For the changes and advances of materials and development of equipment and procedures in the interventional radiology procedures, further studies and monitoring are needed on dose reference level Korean DAP dose conversion factor for the domestic procedures.

  10. Reference doses and patient size in paediatric radiology

    International Nuclear Information System (INIS)

    Hart, D.; Wall, B.; Shrimpton, P.

    2000-01-01

    There is a wide range in patient size from a newborn baby to a 15 year old adolescent. Reference doses for paediatric radiology can sensibly be established only for specific sizes of children. Here five standard sizes have been chosen, representing 0 (newborn), 1, 5, 10 and 15 year old patients. This selection of standard ages has the advantage of matching the paediatric mathematical phantoms which are often used in Monte Carlo organ dose calculations. A method has been developed for calculating factors for normalising doses measured on individual children to those for the nearest standard-sized 'child'. These normalisation factors for entrance surface dose (ESD) and dose-area product (DAP) measurements depend on the thickness of the real child, the thickness of the nearest standard 'child', and an effective linear attenuation coefficient (μ) which is itself a function of the x-ray spectrum, the field size, and whether or not an antiscatter grid is used. Entrance and exit dose measurements were made with phantom material representing soft tissue to establish μ values for abdominal and head examinations, and with phantom material representing lung for chest examinations. These measurements of μ were confirmed and extended to other x-ray spectra and field sizes by Monte Carlo calculations. The normalisation factors are tabulated for ESD measurements for specific radiographic projections through the head and trunk, and for DAP measurements for complete multiprojection examinations in the trunk. The normalisation factors were applied to European survey data for entrance surface dose and dose-area product measurements to derive provisional reference doses for common radiographic projections and for micturating cystourethrography (MCU) examinations - the most frequent fluoroscopic examination on children. (author)

  11. Radiological impact assessment of arc welding supplies rutile

    International Nuclear Information System (INIS)

    Rozas Guinea, S.; Herranz Soler, M.; Perez Marin, C.; Idoeta Hermandorena, R.; Alegria gutierrez, N.; Nunez-Lagos Rogla, R.; Legarda Ibanez, F.

    2013-01-01

    Consumables for welding containing rutile, the coating of the electrode or the filling of tubular thread, are the most widely used and also the most radioactive since the rutile is a mineral containing traces of natural radionuclides, and is therefore considered Normal Occurring Radioactive Material (NORM). As these electrodes and wire are consumed, small particles, aerosols and gases are emitted to the atmosphere of work, and may be inhaled by the welder. Therefore, and also according to the current regulatory framework and work carried out previously by the author on the radiological impact of the process of manufacture and storage of coated rutile electrodes, the objectives are: 1Calcular the internal dose for inhalation during two types of welding, one with electrodes coated and the other with thread. 2 calculate the external dose due to the deposition of particles in the work environment, slag and the immersion of the soldering iron in the cloud of smoke. 3 to assess the radiological impact. (Author)

  12. Patient radiation doses and reference levels in pediatric interventional radiology

    Energy Technology Data Exchange (ETDEWEB)

    Habib Geryes, Bouchra; Lachaux, Julie; Boddaert, Nathalie; Brunelle, Francis [Hopital Universitaire Necker Enfants Malades, Department of Paediatric Radiology, Paris (France); Bak, Adeline; Ozanne, Augustin; Saliou, Guillaume [Hopital Bicetre, Hopitaux Universitaires Paris-Sud, Department of Neuroradiology, Le Kremlin Bicetre (France); Naggara, Olivier [Hopital Universitaire Necker Enfants Malades, Department of Paediatric Radiology, Paris (France); Centre Hospitalier Sainte-Anne, Universite Paris Descartes Sorbonne Paris Cite, Centre de Psychiatrie et Neurosciences, INSERM S894, DHU Neurovasculaire, Paris (France); Centre Hospitalier Sainte-Anne, Department of Neuroradiology, Universite Paris Descartes, Sorbonne Paris Cite, INSERM UMR894, Paris (France)

    2017-09-15

    To describe, in a multicentric paediatric population, reference levels (RLs) for three interventional radiological procedures. From January 2012 to March 2015, children scheduled for an interventional radiological procedure in two French tertiary centres were retrospectively included and divided into four groups according to age: children younger than 2 years (A1), aged 2-7 years (A5), 8-12 years (A10) and 13-18 years (A15). Three procedures were identified: cerebral digital subtraction angiography (DSA), brain arteriovenous malformation (bAVM) embolization, and head and neck superficial vascular malformation (SVM) percutaneous sclerotherapy. Demographic and dosimetric data, including dose area product (DAP), were collected. 550 procedures were included. For DSA (162 procedures), the proposed RL values in DAP were 4, 18, 12 and 32 Gy.cm{sup 2} in groups A1, A5, A10 and A15, respectively. For bAVM embolization (258 procedures), values were 33, 70, 105 and 88 Gy.cm{sup 2} in groups A1, A5, A10 and A15, respectively. For SVM sclerotherapy (130 procedures), values were 350, 790, 490 and 248 mGy.cm{sup 2} in groups A1, A5, A10 and A15, respectively. Consecutive data were available to permit a proposal of reference levels for three major paediatric interventional radiology procedures. (orig.)

  13. Probabilistic Radiological Performance Assessment Modeling and Uncertainty

    Science.gov (United States)

    Tauxe, J.

    2004-12-01

    A generic probabilistic radiological Performance Assessment (PA) model is presented. The model, built using the GoldSim systems simulation software platform, concerns contaminant transport and dose estimation in support of decision making with uncertainty. Both the U.S. Nuclear Regulatory Commission (NRC) and the U.S. Department of Energy (DOE) require assessments of potential future risk to human receptors of disposal of LLW. Commercially operated LLW disposal facilities are licensed by the NRC (or agreement states), and the DOE operates such facilities for disposal of DOE-generated LLW. The type of PA model presented is probabilistic in nature, and hence reflects the current state of knowledge about the site by using probability distributions to capture what is expected (central tendency or average) and the uncertainty (e.g., standard deviation) associated with input parameters, and propagating through the model to arrive at output distributions that reflect expected performance and the overall uncertainty in the system. Estimates of contaminant release rates, concentrations in environmental media, and resulting doses to human receptors well into the future are made by running the model in Monte Carlo fashion, with each realization representing a possible combination of input parameter values. Statistical summaries of the results can be compared to regulatory performance objectives, and decision makers are better informed of the inherently uncertain aspects of the model which supports their decision-making. While this information may make some regulators uncomfortable, they must realize that uncertainties which were hidden in a deterministic analysis are revealed in a probabilistic analysis, and the chance of making a correct decision is now known rather than hoped for. The model includes many typical features and processes that would be part of a PA, but is entirely fictitious. This does not represent any particular site and is meant to be a generic example. A

  14. Enviromental sampling at remote sites based on radiological screening assessments

    International Nuclear Information System (INIS)

    Ebinger, M.H.; Hansen, W.R.; Wenz, G.; Oxenberg, T.P.

    1996-01-01

    Environmental radiation monitoring (ERM) data from remote sites on the White Sands Missile Range, New Mexico, were used to estimate doses to humans and terrestrial mammals from residual radiation deposited during testing of components containing depleted uranium (DU) and thorium (Th). ERM data were used with the DOE code RESRAD and a simple steady-state pathway code to estimate the potential adverse effects from DU and Th to workers in the contaminated zones, to hunters consuming animals from the contaminated zones, and to terrestrial mammals that inhabit the contaminated zones. Assessments of zones contaminated with DU and Th and DU alone were conducted. Radiological doses from Th and DU in soils were largest with a maximum of about 3.5 mrem y -1 in humans and maximum of about 0.1 mrad d -1 in deer. Dose estimates from DU alone in soils were significantly less with a maximum of about 1 mrem y -1 in humans and about 0.04 mrad d -1 in deer. The results of the dose estimates suggest strongly that environmental sampling in these affected areas can be infrequent and still provide adequate assessments of radiological doses to workers, hunters, and terrestrial mammals

  15. Assessment of radiological properties of wastes from urban decontamination procedures

    International Nuclear Information System (INIS)

    Da Silva, D.N.G.; Guimarães, J.R.D.; Rochedo, E.R.R.; Rochedo, P.R.R.; De Luca, C.

    2015-01-01

    One important activity associated to urban areas contaminated from accidental releases to the atmosphere of nuclear power plants is the management of radioactive wastes generated from decontamination procedures. This include the collection, conditioning, packing, transport and temporary/final disposition. The final destination is defined usually through a political decision. Thus, transport of packed radioactive wastes shall depend on decisions not just under the scope of radiological protection issues. However, the simulations performed to assess doses for the public and decontamination workers allows the estimate of radiological aspects related to the waste generated and these characteristics may be included in a multi-criteria decision tool aiming to support, under the radiological protection point of view, the decision-making process on post-emergency procedures. Important information to decision makers are the type, amount and activity concentration of wastes. This work describes the procedures to be included in the urban area model to account for the assessment of qualitative and quantitative description of wastes. The results will allow the classification of different procedures according to predefined criteria that shall then feed the multi-criteria assessment tool, currently under development, considering basic radiological protection aspects of wastes generated by the different available cleanup procedures on typical tropical urban environments. (authors)

  16. Entrance surface dose measurements in pediatric radiological examinations

    International Nuclear Information System (INIS)

    Ribeiro, L.A.; Yoshimura, E.M.

    2008-01-01

    A survey of pediatric radiological examinations was carried out in a reference pediatric hospital of the city of Sao Paulo, in order to investigate the doses to children undergoing conventional X-ray examinations. The results showed that the majority of pediatric patients are below 4 years, and that about 80% of the examinations correspond to chest projections. Doses to typical radiological examinations were measured in vivo with thermoluminescent dosimeters (LiF: Mg, Ti and LiF: Mg, Cu, P) attached to the skin of the children to determine entrance surface dose (ESD). Also homogeneous phantoms were used to obtain ESD to younger children, because the technique uses a so small kVp that the dosimeters would produce an artifact image in the patient radiograph. Four kinds of pediatric examinations were investigated: three conventional examinations (chest, skull and abdomen) and a fluoroscopic procedure (barium swallow). Relevant information about kVp and mAs values used in the examinations was collected, and we discuss how these parameters can affect the ESD. The ESD values measured in this work are compared to reference levels published by the European Commission for pediatric patients. The results obtained (third-quartile of the ESD distribution) for chest AP examinations in three age groups were: 0.056 mGy (2-4 years old); 0.068 mGy (5-9 years old); 0.069 mGy (10-15 years old). All of them are below the European reference level (0.100 mGy). ESD values measured to the older age group in skull and abdomen AP radiographs (mean values 3.44 and 1.20 mGy, respectively) are above the European reference levels (1.5 mGy to skull and 1.0 mGy to abdomen). ESD values measured in the barium swallow examination reached 10 mGy in skin regions corresponding to thyroid and esophagus. It was noticed during this survey that some technicians use, improperly, X-ray fluoroscopy in conventional examinations to help them in positioning the patient. The results presented here are a

  17. A CONCEPTUAL FRAMEWORK FOR MANAGING RADIATION DOSE TO PATIENTS IN DIAGNOSTIC RADIOLOGY USING REFERENCE DOSE LEVELS.

    Science.gov (United States)

    Almén, Anja; Båth, Magnus

    2016-06-01

    The overall aim of the present work was to develop a conceptual framework for managing radiation dose in diagnostic radiology with the intention to support optimisation. An optimisation process was first derived. The framework for managing radiation dose, based on the derived optimisation process, was then outlined. The outset of the optimisation process is four stages: providing equipment, establishing methodology, performing examinations and ensuring quality. The optimisation process comprises a series of activities and actions at these stages. The current system of diagnostic reference levels is an activity in the last stage, ensuring quality. The system becomes a reactive activity only to a certain extent engaging the core activity in the radiology department, performing examinations. Three reference dose levels-possible, expected and established-were assigned to the three stages in the optimisation process, excluding ensuring quality. A reasonably achievable dose range is also derived, indicating an acceptable deviation from the established dose level. A reasonable radiation dose for a single patient is within this range. The suggested framework for managing radiation dose should be regarded as one part of the optimisation process. The optimisation process constitutes a variety of complementary activities, where managing radiation dose is only one part. This emphasises the need to take a holistic approach integrating the optimisation process in different clinical activities. © The Author 2015. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  18. A conceptual framework for managing radiation dose to patients in diagnostic radiology using reference dose levels

    International Nuclear Information System (INIS)

    Almen, Anja; Baath, Magnus

    2016-01-01

    The overall aim of the present work was to develop a conceptual framework for managing radiation dose in diagnostic radiology with the intention to support optimisation. An optimisation process was first derived. The framework for managing radiation dose, based on the derived optimisation process, was then outlined. The outset of the optimisation process is four stages: providing equipment, establishing methodology, performing examinations and ensuring quality. The optimisation process comprises a series of activities and actions at these stages. The current system of diagnostic reference levels is an activity in the last stage, ensuring quality. The system becomes a reactive activity only to a certain extent engaging the core activity in the radiology department, performing examinations. Three reference dose levels-possible, expected and established-were assigned to the three stages in the optimisation process, excluding ensuring quality. A reasonably achievable dose range is also derived, indicating an acceptable deviation from the established dose level. A reasonable radiation dose for a single patient is within this range. The suggested framework for managing radiation dose should be regarded as one part of the optimisation process. The optimisation process constitutes a variety of complementary activities, where managing radiation dose is only one part. This emphasises the need to take a holistic approach integrating the optimisation process in different clinical activities. (authors)

  19. Management of patient dose in radiology in the UK

    International Nuclear Information System (INIS)

    Martin, C. J.

    2011-01-01

    Programmes to manage patient dose in radiology are becoming a higher priority as the number of imaging examinations and the proportion of higher dose computed tomography (CT) and complex interventional procedures all continue to rise. Such programmes have a number of components and their implementation in UK hospitals, which have been developing such programmes over two decades, is described. As part of any programme to manage patient doses, elements should be in place for both justification and optimisation. The system for justification needs to be robust in order to minimise the number of unnecessary procedures and requires the provision of training in radiation protection for medical and other staff to ensure that they understand the risks. Optimisation of X-ray techniques requires performance tests on equipment at installation and regularly thereafter, linked to surveys of patient doses. Confirming the performance of the available options on fluoroscopy and CT equipment is essential and the information obtained should be available to radiographers and radiologists, so they can make informed choices in developing imaging protocols. Patient doses should be compared with diagnostic reference levels set in terms of measured dose quantities to allow the identification of equipment that is giving higher doses. Taking the next step of analysing results to determine the reasons for high doses is crucial and requires a link with the equipment performance tests and an understanding of the underlying physics. Medical physics services play an important role at the hub of the dose management programme for carrying out tests, organising surveys, making recommendations on optimisation strategies and training other staff in radiation protection, performance testing and dose reduction. Programmes for management of patient doses in UK hospitals were first set up in the late 1980's by medical physicists and have been developed since that time to keep pace with the developments in

  20. Potential effects of climatic change on radiological doses from disposal of Canadian nuclear fuel waste

    International Nuclear Information System (INIS)

    Amiro, B.D.

    1997-01-01

    The environmental assessment of deep geologic disposal of Canadian nuclear fuel waste considers many processes that could affect radionuclide transport to humans over thousands of years. Climatic change is an important feature that will occur over these long times. Glaciation will likely occur within the next 100,000 years over much of Canada, and its impact on radiological doses has been assessed previously. In the present study, we investigate the potential effect of short- term climatic change, usually associated with global warming caused by increases in atmospheric trace gases. We study the main biosphere transport pathways causing a radiological dose to humans from 129 I, which is the most important radionuclide in disposal of Canadian used nuclear fuel. Irrigation of a garden with contaminated well water is the main pathway and it can be affected by changes in temperature and precipitation. A cold, wet climate decreases the need for irrigation, and this decreases the radiological dose. A drastic climatic change, such as an increase in temperature from 10 to 20 degrees C and decrease in precipitation from 0.3 to 0.2 m during the growing season, is estimated to increase the dose by a factor of four. This is a relatively small change compared to the range of doses that arise from the variability and uncertainty in many of the parameters used in the environmental assessment models. Therefore, it is likely that the results of probabilistic dose assessment models can include the consequences of short-term climatic change. 39 refs., 3 figs

  1. Physical dose reconstruction in case of radiological accidents: an asset for the victims' management

    International Nuclear Information System (INIS)

    Huet, Christelle; Trompier, Francois; Clairand, Isabelle; Bottollier-Depois, Jean-Francois

    2008-01-01

    In most cases of radiological accidents caused by an external source, the irradiation is heterogeneous, even for a whole body irradiation. Therefore, more than a whole body dose, estimating the dose distribution in the victim's organism is essential to assess biological damages. This dose distribution can be obtained by physical dosimetric reconstruction methods. The laboratory has developed several techniques based on experimental and numerical dose reconstruction and retrospective dosimetry by ESR in order to assess as accurately as possible and as quickly as possible the dose received and especially its distribution throughout the organism so that the physicians may fine tune their diagnosis and prescribe the most suitable treatment. These last years, these techniques were applied several times and each time the results obtained proved to be essential for the physicians in charge of the victims in order to define the therapeutic strategy. This article proposes a review of the physical dose reconstructions performed in the laboratory for recent radiological accidents focusing on the complementarity of the methods and the gain for the victims' management. (author)

  2. Depleted uranium residual radiological risk assessment for Kosovo sites

    International Nuclear Information System (INIS)

    Durante, Marco; Pugliese, Mariagabriella

    2003-01-01

    During the recent conflict in Yugoslavia, depleted uranium rounds were employed and were left in the battlefield. Health concern is related to the risk arising from contamination of areas in Kosovo with depleted uranium penetrators and dust. Although chemical toxicity is the most significant health risk related to uranium, radiation exposure has been allegedly related to cancers among veterans of the Balkan conflict. Uranium munitions are considered to be a source of radiological contamination of the environment. Based on measurements and estimates from the recent Balkan Task Force UNEP mission in Kosovo, we have estimated effective doses to resident populations using a well-established food-web mathematical model (RESRAD code). The UNEP mission did not find any evidence of widespread contamination in Kosovo. Rather than the actual measurements, we elected to use a desk assessment scenario (Reference Case) proposed by the UNEP group as the source term for computer simulations. Specific applications to two Kosovo sites (Planeja village and Vranovac hill) are described. Results of the simulations suggest that radiation doses from water-independent pathways are negligible (annual doses below 30 μSv). A small radiological risk is expected from contamination of the groundwater in conditions of effective leaching and low distribution coefficient of uranium metal. Under the assumptions of the Reference Case, significant radiological doses (>1 mSv/year) might be achieved after many years from the conflict through water-dependent pathways. Even in this worst-case scenario, DU radiological risk would be far overshadowed by its chemical toxicity

  3. Monte Carlo simulation for radiation dose in children radiology

    International Nuclear Information System (INIS)

    Mendes, Hitalo R.; Tomal, Alessandra

    2016-01-01

    The dosimetry in pediatric radiology is essential due to the higher risk that children have in comparison to adults. The focus of this study is to present how the dose varies depending on the depth in a 10 year old and a newborn, for this purpose simulations are made using the Monte Carlo method. Potential differences were considered 70 and 90 kVp for the 10 year old and 70 and 80 kVp for the newborn. The results show that in both cases, the dose at the skin surface is larger for smaller potential value, however, it decreases faster for larger potential values. Another observation made is that because the newborn is less thick the ratio between the initial dose and the final is lower compared to the case of a 10 year old, showing that it is possible to make an image using a smaller entrance dose in the skin, keeping the same level of exposure at the detector. (author)

  4. Analysis of dose distribution in interventionist radiology professionals

    International Nuclear Information System (INIS)

    Mauricio, Claudia L.P.; Silva, Leonardo Peres; Canevaro, Lucia V.; Luz, Eara de Souza

    2005-01-01

    In this work, an evaluation was made of the distribution of dose received by professionals involved in some procedures of Interventional Radiology at hospitals and clinics in Rio de Janeiro, RJ, Brazil. For these measurements thermoluminescent dosemeters (TLD) of LiF: Mg, Ti (TLD100) were used, positioned at different points of the body of professionals: the hands, knees, neck, forehead and chest, inside and outside the lead apron. The measurements were made by procedure and/or a day of work, and the TLD were calibrated in equivalent operating magnitude of personal dose (Hp (d)) at different depths: 0.07 mm, 3 mm and 10 mm. In some procedures, physicians (holders of service and residents) received significant doses. The results show the importance of the appropriate training of these professionals and the use of personal protective equipment (PPE), such as thyroid shield, which is not always used. Based on these evaluations, some suggestions were made in order to optimize the dose values in these procedures and a discussion on the need for additional monitoring points

  5. An updated dose assessment for Rongelap Island

    Energy Technology Data Exchange (ETDEWEB)

    Robison, W.L.; Conrado, C.L.; Bogen, K.T.

    1994-07-01

    We have updated the radiological dose assessment for Rongelap Island at Rongelap Atoll using data generated from field trips to the atoll during 1986 through 1993. The data base used for this dose assessment is ten fold greater than that available for the 1982 assessment. Details of each data base are presented along with details about the methods used to calculate the dose from each exposure pathway. The doses are calculated for a resettlement date of January 1, 1995. The maximum annual effective dose is 0.26 mSv y{sup {minus}1} (26 mrem y{sup {minus}1}). The estimated 30-, 50-, and 70-y integral effective doses are 0.0059 Sv (0.59 rem), 0.0082 Sv (0.82 rem), and 0.0097 Sv (0.97 rem), respectively. More than 95% of these estimated doses are due to 137-Cesium ({sup 137}Cs). About 1.5% of the estimated dose is contributed by 90-Strontium ({sup 90}Sr), and about the same amount each by 239+240-Plutonium ({sup 239+240}PU), and 241-Americium ({sup 241}Am).

  6. Benchmark problems for radiological assessment codes. Final report

    International Nuclear Information System (INIS)

    Mills, M.; Vogt, D.; Mann, B.

    1983-09-01

    This report describes benchmark problems to test computer codes used in the radiological assessment of high-level waste repositories. The problems presented in this report will test two types of codes. The first type of code calculates the time-dependent heat generation and radionuclide inventory associated with a high-level waste package. Five problems have been specified for this code type. The second code type addressed in this report involves the calculation of radionuclide transport and dose-to-man. For these codes, a comprehensive problem and two subproblems have been designed to test the relevant capabilities of these codes for assessing a high-level waste repository setting

  7. Radiological emergency assessment of local decision support system

    International Nuclear Information System (INIS)

    Breznik, B.; Kusar, A.; Boznar, M.Z.; Mlakar, P.

    2003-01-01

    Local decision support system has been developed based on the needs of Krsko Nuclear Power Plant for quick dose projection and it is one of important features required for proposal of intervention before actual release may occur. Radiological emergency assessment in the case of nuclear accident is based on plant status analysis, radiation monitoring data and on prediction of release of radioactive sources to the environment. There are possibilities to use automatic features to predict release source term and manual options for selection of release parameters. Advanced environmental modelling is used for assessment of atmospheric dispersion of radioactive contamination in the environment. (author)

  8. Consequence Assessment for Potential Scenarios of Radiological Terrorists Events

    International Nuclear Information System (INIS)

    Shin, Hyeongki; Kim, Juyoul

    2007-01-01

    Radiological dispersal device (RDD) means any method used to deliberately disperse radioactive material to create terror or harm. Dirty bomb is an example of RDD, which usually consists of radioactive material and unconventional explosive. Dirty bomb was a problem long before September 11, 2001. In 1987, the Iraqi government tested a one-ton radiological bomb. The Iraqi tests confirmed that a dirty bomb is not effective as weapons of mass destruction (WMD) and that its main value is as a psychological weapon. In 1995, Chechen rebels buried a dirty bomb in a park in Moscow threatening to detonate one in the future if their demands were not met. Another good example of potential dirty bomb effects was an incident in Goiania, Brazil on September 18, 1987, where an orphaned medical source containing 1,375 Ci of Cs-137 resulted the death of four people and extensive environmental contamination. The purposes of radiological terrorists events are not to destroy or damage the target but to disperse radioactivity in the environment. They inflict panic on a public and economic damage by disruption of business. They also have influence on enormous clean-up costs by spreading radioactive contamination including secondary impacts on water supply reservoirs. Generally, two major long-term concerns following a RDD are human health and economic impacts. In this study, we developed potential scenarios of radiological terrorists events and performed their radiological consequence assessments in terms of total effective dose equivalent (TEDE), projected cumulative external and internal dose, and ground deposition of radioactivity

  9. Consequence Assessment for Potential Scenarios of Radiological Terrorists Events

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Hyeongki [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of); Kim, Juyoul [Seoul National University, Seoul (Korea, Republic of)

    2007-07-01

    Radiological dispersal device (RDD) means any method used to deliberately disperse radioactive material to create terror or harm. Dirty bomb is an example of RDD, which usually consists of radioactive material and unconventional explosive. Dirty bomb was a problem long before September 11, 2001. In 1987, the Iraqi government tested a one-ton radiological bomb. The Iraqi tests confirmed that a dirty bomb is not effective as weapons of mass destruction (WMD) and that its main value is as a psychological weapon. In 1995, Chechen rebels buried a dirty bomb in a park in Moscow threatening to detonate one in the future if their demands were not met. Another good example of potential dirty bomb effects was an incident in Goiania, Brazil on September 18, 1987, where an orphaned medical source containing 1,375 Ci of Cs-137 resulted the death of four people and extensive environmental contamination. The purposes of radiological terrorists events are not to destroy or damage the target but to disperse radioactivity in the environment. They inflict panic on a public and economic damage by disruption of business. They also have influence on enormous clean-up costs by spreading radioactive contamination including secondary impacts on water supply reservoirs. Generally, two major long-term concerns following a RDD are human health and economic impacts. In this study, we developed potential scenarios of radiological terrorists events and performed their radiological consequence assessments in terms of total effective dose equivalent (TEDE), projected cumulative external and internal dose, and ground deposition of radioactivity.

  10. Federal Radiological Monitoring and Assessment Center Overview of FRMAC Operations

    International Nuclear Information System (INIS)

    1998-01-01

    In the event of a major radiological emergency, 17 federal agencies with various statutory responsibilities have agreed to coordinate their efforts at the emergency scene under the umbrella of the Federal Radiological Emergency Response Plan. This cooperative effort will ensure that all federal radiological assistance fully supports their efforts to protect the public. the mandated federal cooperation ensures that each agency can obtain the data critical to its specific responsibilities. This Overview of Federal Radiological Monitoring and Assessment Center (FRMAC) describes the FRMAC response activities to a major radiological emergency. It also describes the federal assets and subsequent operational activities which provide federal radiological monitoring and assessment of the off-site areas

  11. Assessment of Chemical and Radiological Vulnerabilities

    International Nuclear Information System (INIS)

    SETH, S.S.

    2000-01-01

    Following the May 14, 1997 chemical explosion at Hanford's Plutonium Reclamation Facility, the Department of Energy Richland Operations Office and its prime contractor, Fluor Hanford, Inc., completed an extensive assessment to identify and address chemical and radiological safety vulnerabilities at all facilities under the Project Hanford Management Contract. This was a challenging undertaking because of the immense size of the problem, unique technical issues, and competing priorities. This paper focuses on the assessment process, including the criteria and methodology for data collection, evaluation, and risk-based scoring. It does not provide details on the facility-specific results and corrective actions, but discusses the approach taken to address the identified vulnerabilities

  12. Radiological assessments, environmental monitoring, and study design

    International Nuclear Information System (INIS)

    Hansen, W.R.; Elle, D.R.

    1980-01-01

    Studies of the behavior of transuranic elements in the environment form the basic data for applied programs in radiological assessment, environmental monitoring, derivation of radiation-protection standards, and environmental impact statements. This chapter introduces some of the major information requirements of these applications of transuranic research data. Characteristics of the source terms from nuclear activities usually are needed for an analysis of environmental pathways or deployment of monitoring systems. Major inhalation and ingestion pathways are considered in assessments of hazards from transuranics and are discussed from the viewpoint of research needed

  13. Northern Marshall Islands radiological survey: terrestrial food chain and total doses

    International Nuclear Information System (INIS)

    Robison, W.L.; Mount, M.E.; Phillips, W.A.; Conrado, C.A.; Stuart, M.L.; Stoker, C.E.

    1982-01-01

    A radiological survey was conducted from September through November of 1978 to assess the concentrations of persistent manmade radionuclides in the terrestrial and marine environments of 11 atolls and 2 islands in the Northern Marshall Islands. The survey consisted mainly of an aerial radiological reconnaissance to map the external gamma-ray exposure rates over the islands of each atoll. The logistical support for the entire survey was designed to accommodate this operation. As a secondary phase of the survey, shore parties collected appropriate terrestrial and marine samples to assess the radiological dose from pertinent food chains to those individuals residing on the atolls, who may in the future reside on some of the presently uninhabited atolls, or who collect food from these atolls. Over 5000 terrestrial and marine samples were collected for radionuclide analysis from 76 different islands. Soils, vegetation, indigenous animals, and cistern water and groundwater were collected from the islands. Reef and pelagic fish, clams, lagoon water, and sediments were obtained from the lagoons. The concentration data for 90 Sr, 137 Cs, 238 Pu, 239 240 Pu, and 241 Am in terrestrial food crops, fowl, and animals collected at the atolls or islands are summarized. An assessment of the total dose from the major exposure pathways including external gamma, terrestrial food chain including food products and drinking water, marine food chain, and inhalation is provided. Radiological doses at each atoll or island are calculated from the average radionuclide concentrations in the terrestrial foods, marine foods, etc. assuming the average daily intake for each food item

  14. Radiological impact assessment in Malaysia using RESRAD computer code

    International Nuclear Information System (INIS)

    Syed Hakimi Sakuma Syed Ahmad; Khairuddin Mohamad Kontol; Razali Hamzah

    1999-01-01

    Radiological Impact Assessment (RIA) can be conducted in Malaysia by using the RESRAD computer code developed by Argonne National Laboratory, U.S.A. The code can do analysis to derive site specific guidelines for allowable residual concentrations of radionuclides in soil. Concepts of the RIA in the context of waste management concern in Malaysia, some regulatory information and assess status of data collection are shown. Appropriate use scenarios and site specific parameters are used as much as possible so as to be realistic so that will reasonably ensure that individual dose limits and or constraints will be achieved. Case study have been conducted to fulfil Atomic Energy Licensing Board (AELB) requirements where for disposal purpose the operator must be required to carry out. a radiological impact assessment to all proposed disposals. This is to demonstrate that no member of public will be exposed to more than 1 mSv/year from all activities. Results obtained from analyses show the RESRAD computer code is able to calculate doses, risks, and guideline values. Sensitivity analysis by the computer code shows that the parameters used as input are justified so as to improve confidence to the public and the AELB the results of the analysis. The computer code can also be used as an initial assessment to conduct screening assessment in order to determine a proper disposal site. (Author)

  15. Application of the ICRP approach for radiological protection of the marine environment in generic impact assessments

    Energy Technology Data Exchange (ETDEWEB)

    Kliaus, Viktoryia [Republican Scientific-Practical Centre of Hygiene, Laboratory of Radiation Safety, Akademicheskaya str. 8, 220012, Minsk (Belarus); Telleria, Diego M. [IAEA-Assessment and Management of Environmental Releases Unit, Wagramer Strasse 5 - PO Box 100, A-1400, Vienna (Austria); Cabianca, Tiberio [Centre for Radiation, Chemical and Environmental Hazards, PHE, Chilton, Didcot, Oxfordshire OX11 0RQ (United Kingdom)

    2014-07-01

    This paper presents a way to use the ICRP approach for protection of the environment in generic assessments of the radiological impact of radioactive releases to the marine environment. Generic assessments of radiological impact to the environment are needed in certain circumstances, for example, when input data are limited or when the likely radiological consequences are expected to be not significant. Under these circumstances the effort in performing the assessment must be commensurate with the potential radiological consequences. The generic assessment described in this paper is a simple tool which provides reasonable and cautious results and is applicable to multiple exposure scenarios associated with the assessment of the radiological impact of releases to the marine the environment. This generic assessment can be also used to provide preliminary results which, when compared to radiological criteria, may determine the need of further specific assessments. The ICRP based its approach to protect the environment in the definition of a set of reference animals and plants and the use of related radiological criteria, in the form of derived consideration reference levels. The paper discusses selection and exposure conditions of the reference animals and plants, methods to estimate their doses and the use of the radiological criteria, for the purpose of a generic assessment. The IAEA is elaborating applications of these generic impact assessments presented in the paper to be included in international guidance under development. (authors)

  16. Estimation of dose challenge in radiological exams policontuses patients in public hospital in Santiago with digital radiology equipment

    International Nuclear Information System (INIS)

    Diaz-Munoz Ihmaidan, Gabriela

    2012-01-01

    lonizing radiation is always present in our natural environment and with the development of new technologies in diagnostic radiology we have elevated the exposure to radiation with an increased dose to both patient and professionals. This is of great importance for secondary stochastic effects that could be generated by exposure to ionizing radiation. There are different x-ray entrance dose studies in patients with radiological examinations in conventional radiology equipment, but not in trauma patients examinated with digital radiology equipment where there is a supposed greater exposure to radiation because of the increase of the number of radiological examinations requested. This study determined the doses received by trauma patients in a direct digital x ray equipment (in a ER in Santiago, Chile) and see if the doses are within the ones recommended by international societies. We used thermoluminescent crystals which were first properly calibrated and located in the center of the radiation beam. The results obtained show that using good practice we can obtain acceptable dose levels, independently of the digital equipment used where it is presumed that could give a higher dose of ionizing radiation exposure than conventional x-ray equipment

  17. Chloral hydrate sedation in radiology: retrospective audit of reduced dose

    International Nuclear Information System (INIS)

    Bracken, Jennifer; Heaslip, Ingrid; Ryan, Stephanie

    2012-01-01

    Chloral hydrate (CH) is safe and effective for sedation of suitable children. The purpose of this study was to assess whether adequate sedation is achieved with reduced CH doses. We retrospectively recorded outpatient CH sedations over 1 year. We defined standard doses of CH as 50 mg/kg (infants) and 75 mg/kg (children >1 year). A reduced dose was defined as at least 20% lower than the standard dose. In total, 653 children received CH sedation (age, 1 month-3 years 10 months), 42% were given a reduced initial dose. Augmentation dose was required in 10.9% of all children, and in a higher proportion of children >1 year (15.7%) compared to infants (5.7%; P 1 year (95.3%; P = 0.03). A reduced initial dose had no negative effect on outcome (P = 0.19) or time to sedation. No significant complications were seen. We advocate sedation with reduced CH doses (40 mg/kg for infants; 60 mg/kg for children >1 year of age) for outpatient imaging procedures when the child is judged to be quiet or sleepy on arrival. (orig.)

  18. Chloral hydrate sedation in radiology: retrospective audit of reduced dose

    Energy Technology Data Exchange (ETDEWEB)

    Bracken, Jennifer [Children' s University Hospital, Radiology Department, Dublin (Ireland); Royal Children' s Hospital, Department of Medical Imaging, Parkville, Victoria (Australia); Heaslip, Ingrid; Ryan, Stephanie [Children' s University Hospital, Radiology Department, Dublin (Ireland)

    2012-03-15

    Chloral hydrate (CH) is safe and effective for sedation of suitable children. The purpose of this study was to assess whether adequate sedation is achieved with reduced CH doses. We retrospectively recorded outpatient CH sedations over 1 year. We defined standard doses of CH as 50 mg/kg (infants) and 75 mg/kg (children >1 year). A reduced dose was defined as at least 20% lower than the standard dose. In total, 653 children received CH sedation (age, 1 month-3 years 10 months), 42% were given a reduced initial dose. Augmentation dose was required in 10.9% of all children, and in a higher proportion of children >1 year (15.7%) compared to infants (5.7%; P < 0.001). Sedation was successful in 96.7%, and more frequently successful in infants (98.3%) than children >1 year (95.3%; P = 0.03). A reduced initial dose had no negative effect on outcome (P = 0.19) or time to sedation. No significant complications were seen. We advocate sedation with reduced CH doses (40 mg/kg for infants; 60 mg/kg for children >1 year of age) for outpatient imaging procedures when the child is judged to be quiet or sleepy on arrival. (orig.)

  19. Status of safety technology for radiological consequence assessment of postulated accidents in liquid metal fast breeder reactors, Canoga Park, California, 29 July--31 July 1975

    International Nuclear Information System (INIS)

    1975-07-01

    State-of-the-art capabilities are examined for prediction and mitigation of radiological consequences of postulated LMFBR accidents. The following topics are treated: radioactive source terms, sodium reactions, aerosol behavior, radiological dose assessment, and engineered safeguards. (U.S.)

  20. Double dosimetry procedures for the determination of occupational effective dose in interventional radiology

    International Nuclear Information System (INIS)

    Jaervinen, H.; Buls, N.; Clerinx, P.; Miljanic, S.; Ranogajec-Komor, M.; Nikodemova, D.; D'Errico, F.

    2008-01-01

    Full text: In interventional radiology, for an accurate determination of occupational effective dose, measurements with two dosemeters ('double dosimetry', DD) have been recommended, one dosemeter located above and one under the protective apron. In this paper, based on an extensive literature search, the most recent algorithms developed for the determination of effective dose from the dosimeter readings have been compared for a few practical interventional procedures. Recommendations on the practices and algorithms are given on the basis of the results. For the comparison of algorithms, dosemeter readings and the effective dose were obtained both experimentally and by calculation. Further, data from published Monte Carlo calculations have been applied. The literature review has indicated that very few regulations for DD exist and the DD practices have not been harmonized. There is no firm consensus on the most suitable calculation algorithms. Single dosemeter (SD) measurements are still mostly used for the calculation of effective dose. Most DD and SD algorithms overestimate effective dose significantly, sometimes by over ten times. However, SD algorithms can significantly underestimate effective dose in certain interventional radiology conditions. Due to the possibility of underestimating effective dose, DD is generally recommended. The results suggest that there might not be a single DD algorithm which would be optimum for all interventional radiology procedures. However, the selection of a precise DD algorithm for each individual condition is not practical and compromises must be made. For accurate personnel dosimetry, the accuracy of the algorithm selected should be tested for typical local interventional radiology condition. Personnel dosemeters should be used in the recommended positions. The dosemeter above the apron should be on a collar and its reading also used to assess the risk of lens injuries. The dosemeter under the apron can be on the chest or

  1. Radiological impact assessment within the IAEA Arctic Assessment Project (IASAP)

    DEFF Research Database (Denmark)

    Scott, E.M.; Gurbutt, P.; Harmes, I.

    1998-01-01

    As part of the International Arctic Seas Assessment Project (IASAP) of IAEA, a working group was created to model the dispersal and transfer of radionuclides released from radioactive waste disposed of in the Kara Sea and bays of Novaya Zemlya and to assess the radiological impact. Existing models...

  2. Probabilistic assessment of the radiological consequences of radioactive waste disposal

    International Nuclear Information System (INIS)

    Smith, C.F.; Cohen, J.J.

    1989-01-01

    Conventional methods for prediction of radiological dose consequence of low level radioactive waste (LLW) disposal generally involve application of deterministic calculational modeling. Since the selection of parametric input values for such analyses is made on a conservative ('worst case') basis, the results can be subject to criticism as being unrealistically high. To address this problem, a method for probabilistic assessment has been developed in which input parameters are expressed as probability distribution functions. An example calculation is presented for the impacts from migration of Carbon-14 to a close-in well. (author). 4 refs.; 1 tab

  3. Radiological assessments of land disposal options: recent model developments

    International Nuclear Information System (INIS)

    Fearn, H.S.; Pinner, A.V.; Hemming, C.R.

    1984-10-01

    This report describes progress in the development of methodologies and models for assessing the radiological impact of the disposal of low and intermediate level wastes by (i) shallow land burial in simple trenches (land 1), (ii) shallow land burial in engineered facilities (land 2), and (iii) emplacement in mined repositories or existing cavities (land 3/4). In particular the report describes wasteform leaching models, for unconditioned and cemented waste, the role of engineered barriers of a shallow land burial facility in reducing the magnitude of doses arising from groundwater contact and a detailed consideration of the interactions between radioactive carbon and various media. (author)

  4. Radiological dose reconstruction for birds reconciles outcomes of Fukushima with knowledge of dose-effect relationships

    International Nuclear Information System (INIS)

    Garnier-Laplace, Jacqueline; Beaugelin-Seiller, Karine; Della-Vedova, Claire; Metivier, Jean-Michel; Ritz, Christian; Mousseau, Timothy A.; Pape Moeller, Anders

    2015-01-01

    We reconstructed the radiological dose for birds observed at 300 census sites in the 50-km northwest area affected by the accident at the Fukushima Daiichi nuclear power plant over 2011-2014. Substituting the ambient dose rate measured at the census points (from 0.16 to 31 μGy h -1 ) with the dose rate reconstructed for adult birds of each species (from 0.3 to 97 μGy h -1 ), we confirmed that the overall bird abundance at Fukushima decreased with increasing total doses. This relationship was directly consistent with exposure levels found in the literature to induce physiological disturbances in birds. Among the 57 species constituting the observed bird community, we found that 90% were likely chronically exposed at a dose rate that could potentially affect their reproductive success. We quantified a loss of 22.6% of the total number of individuals per increment of one unit log10-transformed total dose (in Gy), over the four-year post-accident period in the explored area. We estimated that a total dose of 0.55 Gy reduced by 50% the total number of birds in the study area over 2011-2014. The data also suggest a significant positive relationship between total dose and species diversity. (authors)

  5. MO-DE-204-00: International Symposium: Patient Dose Reduction in Diagnostic Radiology

    International Nuclear Information System (INIS)

    2016-01-01

    The main topic of the session is to show how dose optimization is being implemented in various regions of the world, including Europe, Australia, North America and other regions. A multi-national study conducted under International Atomic Energy Agency (IAEA) across more than 50 less resourced countries gave insight into patient radiation doses and safety practices in CT, mammography, radiography and interventional procedures, both for children and adults. An important outcome was the capability development on dose assessment and management. An overview of recent European projects related to CT radiation dose and optimization both to adults and children will be presented. Existing data on DRLs together with a European methodology proposed on establishing and using DRLs for paediatric radiodiagnostic imaging and interventional radiology practices will be shown. Compared with much of Europe at least, many Australian imaging practices are relatively new to the task of diagnostic imaging dose optimisation. In 2008 the Australian Government prescribed a requirement to periodically compare patient radiation doses with diagnostic reference levels (DRLs), where DRLs have been established. Until recently, Australia had only established DRLs for computed tomography (CT). Regardless, both professional society and individual efforts to improved data collection and develop optimisation strategies across a range of modalities continues. Progress in this field, principally with respect to CT and interventional fluoroscopy will be presented. In the US, dose reduction and optimization efforts for computed tomography have been promoted and mandated by several organizations and accrediting entities. This presentation will cover the general motivation, implementation, and implications of such efforts. Learning Objectives: Understand importance of the dose optimization in Diagnostic Radiology. See how this goal is achieved in different regions of the World. Learn about the global trend

  6. Rapid radiological characterization method based on the use of dose coefficients

    International Nuclear Information System (INIS)

    Dulama, C.; Toma, Al.; Dobrin, R.; Valeca, M.

    2010-01-01

    Intervention actions in case of radiological emergencies and exploratory radiological surveys require rapid methods for the evaluation of the range and extent of contamination. When simple and homogeneous radionuclide composition characterize the radioactive contamination, surrogate measurements can be used to reduce the costs implied by laboratory analyses and to speed-up the process of decision support. A dose-rate measurement-based methodology can be used in conjunction with adequate dose coefficients to assess radionuclide inventories and to calculate dose projections for various intervention scenarios. The paper presents the results obtained for dose coefficients in some particular exposure geometries and the methodology used for deriving dose rate guidelines from activity concentration upper levels specified as contamination limits. All calculations were performed by using the commercial software MicroShield from Grove Software Inc. A test case was selected as to meet the conditions from EPA Federal Guidance Report no. 12 (FGR12) concerning the evaluation of dose coefficients for external exposure from contaminated soil and the obtained results were compared to values given in the referred document. The geometries considered as test cases are: contaminated ground surface; - infinite extended homogeneous surface contamination and soil contaminated to a depth of 15 cm. As shown by the results, the values agree within 50% relative difference for most of the cases. The greatest discrepancies were observed for depth contamination simulation and in the case of radionuclides with complicated gamma emission and this is due to the different approach from MicroShield and FGR12. A case study is presented for validation of the methodology, where both dose rate measurements and laboratory analyses were performed on an extended quasi-homogeneous NORM contamination. The dose rate estimations obtained by applying the dose coefficients to the radionuclide concentrations

  7. MO-DE-204-03: Radiology Dose Optimisation - An Australian Perspective

    International Nuclear Information System (INIS)

    Schick, D.

    2016-01-01

    The main topic of the session is to show how dose optimization is being implemented in various regions of the world, including Europe, Australia, North America and other regions. A multi-national study conducted under International Atomic Energy Agency (IAEA) across more than 50 less resourced countries gave insight into patient radiation doses and safety practices in CT, mammography, radiography and interventional procedures, both for children and adults. An important outcome was the capability development on dose assessment and management. An overview of recent European projects related to CT radiation dose and optimization both to adults and children will be presented. Existing data on DRLs together with a European methodology proposed on establishing and using DRLs for paediatric radiodiagnostic imaging and interventional radiology practices will be shown. Compared with much of Europe at least, many Australian imaging practices are relatively new to the task of diagnostic imaging dose optimisation. In 2008 the Australian Government prescribed a requirement to periodically compare patient radiation doses with diagnostic reference levels (DRLs), where DRLs have been established. Until recently, Australia had only established DRLs for computed tomography (CT). Regardless, both professional society and individual efforts to improved data collection and develop optimisation strategies across a range of modalities continues. Progress in this field, principally with respect to CT and interventional fluoroscopy will be presented. In the US, dose reduction and optimization efforts for computed tomography have been promoted and mandated by several organizations and accrediting entities. This presentation will cover the general motivation, implementation, and implications of such efforts. Learning Objectives: Understand importance of the dose optimization in Diagnostic Radiology. See how this goal is achieved in different regions of the World. Learn about the global trend

  8. MO-DE-204-03: Radiology Dose Optimisation - An Australian Perspective

    Energy Technology Data Exchange (ETDEWEB)

    Schick, D. [Princess Alexandra Hospital (United States)

    2016-06-15

    The main topic of the session is to show how dose optimization is being implemented in various regions of the world, including Europe, Australia, North America and other regions. A multi-national study conducted under International Atomic Energy Agency (IAEA) across more than 50 less resourced countries gave insight into patient radiation doses and safety practices in CT, mammography, radiography and interventional procedures, both for children and adults. An important outcome was the capability development on dose assessment and management. An overview of recent European projects related to CT radiation dose and optimization both to adults and children will be presented. Existing data on DRLs together with a European methodology proposed on establishing and using DRLs for paediatric radiodiagnostic imaging and interventional radiology practices will be shown. Compared with much of Europe at least, many Australian imaging practices are relatively new to the task of diagnostic imaging dose optimisation. In 2008 the Australian Government prescribed a requirement to periodically compare patient radiation doses with diagnostic reference levels (DRLs), where DRLs have been established. Until recently, Australia had only established DRLs for computed tomography (CT). Regardless, both professional society and individual efforts to improved data collection and develop optimisation strategies across a range of modalities continues. Progress in this field, principally with respect to CT and interventional fluoroscopy will be presented. In the US, dose reduction and optimization efforts for computed tomography have been promoted and mandated by several organizations and accrediting entities. This presentation will cover the general motivation, implementation, and implications of such efforts. Learning Objectives: Understand importance of the dose optimization in Diagnostic Radiology. See how this goal is achieved in different regions of the World. Learn about the global trend

  9. MO-DE-204-00: International Symposium: Patient Dose Reduction in Diagnostic Radiology

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2016-06-15

    The main topic of the session is to show how dose optimization is being implemented in various regions of the world, including Europe, Australia, North America and other regions. A multi-national study conducted under International Atomic Energy Agency (IAEA) across more than 50 less resourced countries gave insight into patient radiation doses and safety practices in CT, mammography, radiography and interventional procedures, both for children and adults. An important outcome was the capability development on dose assessment and management. An overview of recent European projects related to CT radiation dose and optimization both to adults and children will be presented. Existing data on DRLs together with a European methodology proposed on establishing and using DRLs for paediatric radiodiagnostic imaging and interventional radiology practices will be shown. Compared with much of Europe at least, many Australian imaging practices are relatively new to the task of diagnostic imaging dose optimisation. In 2008 the Australian Government prescribed a requirement to periodically compare patient radiation doses with diagnostic reference levels (DRLs), where DRLs have been established. Until recently, Australia had only established DRLs for computed tomography (CT). Regardless, both professional society and individual efforts to improved data collection and develop optimisation strategies across a range of modalities continues. Progress in this field, principally with respect to CT and interventional fluoroscopy will be presented. In the US, dose reduction and optimization efforts for computed tomography have been promoted and mandated by several organizations and accrediting entities. This presentation will cover the general motivation, implementation, and implications of such efforts. Learning Objectives: Understand importance of the dose optimization in Diagnostic Radiology. See how this goal is achieved in different regions of the World. Learn about the global trend

  10. Entrance surface dose in cerebral interventional radiology procedures

    International Nuclear Information System (INIS)

    Barrera-Rico, M.; López-Rendón, X.; Rivera-Ordóñez, C. E.; Gamboa-deBuen, I.

    2012-01-01

    At the Instituto Nacional de Neurología y Neurocirugía (INNN) diagnostic as well as therapeutic procedures of interventional radiology are carried out. Since the procedures can last from some minutes to several hours, the absorbed dose for the patient could increase dangerously. An investigation had begun in order to determine the entrance surface dose (ESD) using 25 thermoluminiscent dosimeters TLD-100 and 8 strips of 15 ×1 cm 2 of Gafchromic XR-QA2 film bound in a holder of 15×15 cm 2 in the posteroanterior (PA) and lateral (LAT) positions during all the procedure. The results show that maximum ESD could be from 0.9 to 2.9 Gy for the PA position and between 1.6 and 2.5 Gy for the lateral position. The average ESD was between 0.7 and 1.3 Gy for the PA position, and from 0.44 to 1.1 Gy for the lateral position in a therapeutic procedure.

  11. Entrance surface dose in cerebral interventional radiology procedures

    Energy Technology Data Exchange (ETDEWEB)

    Barrera-Rico, M.; Lopez-Rendon, X.; Rivera-Ordonez, C. E.; Gamboa-deBuen, I. [Instituto de Ciencias Nucleares, Universidad Nacional Autonoma de Mexico, 04510 DF (Mexico); Instituto Nacional de Neurologia y Neurocirugia Manuel Velasco Suarez, 14269 DF (Mexico); Instituto de Ciencias Nucleares, Universidad Nacional Autonoma de Mexico, 04510 DF (Mexico)

    2012-10-23

    At the Instituto Nacional de Neurologia y Neurocirugia (INNN) diagnostic as well as therapeutic procedures of interventional radiology are carried out. Since the procedures can last from some minutes to several hours, the absorbed dose for the patient could increase dangerously. An investigation had begun in order to determine the entrance surface dose (ESD) using 25 thermoluminiscent dosimeters TLD-100 and 8 strips of 15 Multiplication-Sign 1 cm{sup 2} of Gafchromic XR-QA2 film bound in a holder of 15 Multiplication-Sign 15 cm{sup 2} in the posteroanterior (PA) and lateral (LAT) positions during all the procedure. The results show that maximum ESD could be from 0.9 to 2.9 Gy for the PA position and between 1.6 and 2.5 Gy for the lateral position. The average ESD was between 0.7 and 1.3 Gy for the PA position, and from 0.44 to 1.1 Gy for the lateral position in a therapeutic procedure.

  12. Patient dose in interventional radiology: a multicentre study of the most frequent procedures in France

    International Nuclear Information System (INIS)

    Etard, Cecile; Bigand, Emeline; Salvat, Cecile; Vidal, Vincent; Beregi, Jean Paul; Hornbeck, Amaury; Greffier, Joel

    2017-01-01

    A national retrospective survey on patient doses was performed by the French Society of Medical physicists to assess reference levels (RLs) in interventional radiology as required by the European Directive 2013/59/Euratom. Fifteen interventional procedures in neuroradiology, vascular radiology and osteoarticular procedures were analysed. Kerma area product (KAP), fluoroscopy time (FT), reference air kerma and number of images were recorded for 10 to 30 patients per procedure. RLs were calculated as the 3rd quartiles of the distributions. Results on 4600 procedures from 36 departments confirmed the large variability in patient dose for the same procedure. RLs were proposed for the four dosimetric estimators and the 15 procedures. RLs in terms of KAP and FT were 90 Gm.cm 2 and 11 mins for cerebral angiography, 35 Gy.cm 2 and 16 mins for biliary drainage, 75 Gy.cm 2 and 6 mins for lower limbs arteriography and 70 Gy.cm 2 and 11 mins for vertebroplasty. For these four procedures, RLs were defined according to the complexity of the procedure. For all the procedures, the results were lower than most of those already published. This study reports RLs in interventional radiology based on a national survey. Continual evolution of practices and technologies requires regular updates of RLs. (orig.)

  13. Patient dose in interventional radiology: a multicentre study of the most frequent procedures in France

    Energy Technology Data Exchange (ETDEWEB)

    Etard, Cecile [Institut de Radioprotection et de Surete Nucleaire, Fontenay-aux-Roses (France); French Society of Medical Physicists (SFPM), Paris (France); Bigand, Emeline [French Society of Medical Physicists (SFPM), Paris (France); La Timone University Hospital, Department of Radiology, Marseille Cedex (France); Salvat, Cecile [French Society of Medical Physicists (SFPM), Paris (France); Lariboisiere Hospital, Department of Medical Physics and Radiation Protection, Paris (France); Vidal, Vincent [La Timone University Hospital, Department of Radiology, Marseille Cedex (France); French Society of Radiology (SFR) - Interventional Radiology Federation (FRI), Paris (France); Beregi, Jean Paul [French Society of Radiology (SFR) - Interventional Radiology Federation (FRI), Paris (France); Nimes University Hospital, Medical Imaging Group Nimes, Department of Radiology, Nimes (France); Hornbeck, Amaury [French Society of Medical Physicists (SFPM), Paris (France); Trousseau University Hospital, Department of Pediatric Radiology, Paris (France); Greffier, Joel [French Society of Medical Physicists (SFPM), Paris (France); Nimes University Hospital, Medical Imaging Group Nimes, Department of Radiology, Nimes (France)

    2017-10-15

    A national retrospective survey on patient doses was performed by the French Society of Medical physicists to assess reference levels (RLs) in interventional radiology as required by the European Directive 2013/59/Euratom. Fifteen interventional procedures in neuroradiology, vascular radiology and osteoarticular procedures were analysed. Kerma area product (KAP), fluoroscopy time (FT), reference air kerma and number of images were recorded for 10 to 30 patients per procedure. RLs were calculated as the 3rd quartiles of the distributions. Results on 4600 procedures from 36 departments confirmed the large variability in patient dose for the same procedure. RLs were proposed for the four dosimetric estimators and the 15 procedures. RLs in terms of KAP and FT were 90 Gm.cm{sup 2} and 11 mins for cerebral angiography, 35 Gy.cm{sup 2} and 16 mins for biliary drainage, 75 Gy.cm{sup 2} and 6 mins for lower limbs arteriography and 70 Gy.cm{sup 2} and 11 mins for vertebroplasty. For these four procedures, RLs were defined according to the complexity of the procedure. For all the procedures, the results were lower than most of those already published. This study reports RLs in interventional radiology based on a national survey. Continual evolution of practices and technologies requires regular updates of RLs. (orig.)

  14. Radiological assessment for bauxite mining and alumina refining.

    Science.gov (United States)

    O'Connor, Brian H; Donoghue, A Michael; Manning, Timothy J H; Chesson, Barry J

    2013-01-01

    Two international benchmarks assess whether the mining and processing of ores containing Naturally Occurring Radioactive Material (NORM) require management under radiological regulations set by local jurisdictions. First, the 1 Bq/g benchmark for radionuclide head of chain activity concentration determines whether materials may be excluded from radiological regulation. Second, processes may be exempted from radiological regulation where occupational above-background exposures for members of the workforce do not exceed 1 mSv/year. This is also the upper-limit of exposure prescribed for members of the public. Alcoa of Australia Limited (Alcoa) has undertaken radiological evaluations of the mining and processing of bauxite from the Darling Range of Western Australia since the 1980s. Short-term monitoring projects have demonstrated that above-background exposures for workers do not exceed 1 mSv/year. A whole-of-year evaluation of above-background, occupational radiological doses for bauxite mining, alumina refining and residue operations was conducted during 2008/2009 as part of the Alcoa NORM Quality Assurance System (NQAS). The NQAS has been guided by publications from the International Commission on Radiological Protection (ICRP), the International Atomic Energy Agency (IAEA) and the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA). The NQAS has been developed specifically in response to implementation of the Australian National Directory on Radiation Protection (NDRP). Positional monitoring was undertaken to increase the accuracy of natural background levels required for correction of occupational exposures. This is important in view of the small increments in exposure that occur in bauxite mining, alumina refining and residue operations relative to natural background. Positional monitoring was also undertaken to assess the potential for exposure in operating locations. Personal monitoring was undertaken to characterise exposures in Similar

  15. Inhalation dose assessment for Maralinga and Emu

    International Nuclear Information System (INIS)

    Johnston, P.N.; Lokan, K.H.; Williams, G.A.

    1990-01-01

    Dose assessments for the inhalation of artificial radionuclides are presented for all types of contaminated areas at Maralinga and Emu. These enable Committed Effective Dose Equivalent (CEDE), to be estimated by scaling at any area of interest where activity concentrations are known. In the case of Aborigines, these dose are estimated assuming respirable dust loadings of 1 mg/m 3 for adults and 1.5 mg/m 3 for children and infants. Details of the calculations are presented in the appendix. The model of the respiratory system used in this assessment is that described in Interantional Commission on Radiological Protection (ICRP) Publication 30 (ICRP, 1979a). With the exception of Kuli, which is contaminated with uranium, at all other sites it is only the inhalation of plutonium and americium that contributes significantly to the dose, and of these 239 Pu is the largest contributor. Therefore, considering the long half lives of the radionuclides concerned, it appears that the inhalation problems highlighted by this dose assessment will not diminish significantly within any reasonable period of time and hence management strategies must be developed to deal with such problems. 32 refs., 5 tabs., 1 fig

  16. Models and parameters for environmental radiological assessments

    International Nuclear Information System (INIS)

    Miller, C.W.

    1983-01-01

    This article reviews the forthcoming book Models and Parameters for Environmental Radiological Assessments, which presents a unified compilation of models and parameters for assessing the impact on man of radioactive discharges, both routine and accidental, into the environment. Models presented in this book include those developed for the prediction of atmospheric and hydrologic transport and deposition, for terrestrial and aquatic food-chain bioaccumulation, and for internal and external dosimetry. Summaries are presented for each of the transport and dosimetry areas previously for each of the transport and dosimetry areas previously mentioned, and details are available in the literature cited. A chapter of example problems illustrates many of the methodologies presented throughout the text. Models and parameters presented are based on the results of extensive literature reviews and evaluations performed primarily by the staff of the Health and Safety Research Division of Oak Ridge National Laboratory

  17. Principles and issues in radiological ecological risk assessment.

    Science.gov (United States)

    Jones, Daniel; Domotor, Stephen; Higley, Kathryn; Kocher, David; Bilyard, Gordon

    2003-01-01

    This paper provides a bridge between the fields of ecological risk assessment (ERA) and radioecology by presenting key biota dose assessment issues identified in the US Department of Energy's Graded Approach for Evaluating Radiation Doses to Aquatic and Terrestrial Biota in a manner consistent with the US Environmental Protection Agency's framework for ERA. Current radiological ERA methods and data are intended for use in protecting natural populations of biota, rather than individual members of a population. Potentially susceptible receptors include vertebrates and terrestrial plants. One must ensure that all media, radionuclides (including short-lived radioactive decay products), types of radiations (i.e., alpha particles, electrons, and photons), and pathways (i.e., internal and external contamination) are combined in each exposure scenario. The relative biological effectiveness of alpha particles with respect to deterministic effects must also be considered. Expected safe levels of exposure are available for the protection of natural populations of aquatic biota (10 mGy d(-1)) and terrestrial plants (10 mGy d(-1)) and animals (1 mGy d(-1)) and are appropriate for use in all radiological ERA tiers, provided that appropriate exposure assumptions are used. Caution must be exercised (and a thorough justification provided) if more restrictive limits are selected, to ensure that the supporting data are of high quality, reproducible, and clearly relevant to the protection of natural populations.

  18. Malaysian experiences in radiological safety assessment on norm wastes

    International Nuclear Information System (INIS)

    Syed Hakimi Sakuma Syed Ahmad; Khairuddin Mohamad Kontol

    2000-01-01

    Radiological Impact Assessments (RIAs) on proposed disposal sites for NORM wastes were performed in Malaysia. Analysis results were used to derive site specific guidelines for allowable residual concentrations of radionuclides in soil, calculation of doses and risks. Appropriate use scenarios and site specific parameters were used as much as possible so as to be realistic so that will reasonably ensure that individual dose limits and or constraints will be achieved. Disposals were performed to fulfil Atomic Energy Licensing Board of Malaysia (AELB) requirements for which the operator must carry out a radiological impact assessment. This is to demonstrate that no member of public will be exposed to more than 1 mSv/year from all activities. Fatal cancer risk factor is 5x10 -2 per man.Sv. Radionuclides of main concern are radium-226 and radium-228 which are considered as toxic. Sensitivity and uncertainty analyses were performed to show that the parameters used as input into the computer model were justified so as to improve confidence of the public and the AELB in respect of the results of the analysis. Case study to determine a proposed near surface disposal site for treated oil sludge was described. (author)

  19. Evaluation of radiological doses to the terrestrial plants around Trombay

    International Nuclear Information System (INIS)

    Ajay Kumar; Singhal, R.K.; Preetha, J.; Joshi, S.N.; Hegde, A.G.

    2005-01-01

    Existing policies for radiation protection do not provide explicit criteria for the protection of species other than humans, i.e. not for flora and fauna. Concern over this omission is now being widely expressed and moves are under way to evaluate the doses to terrestrial and aquatic biota. During the present work radiological doses (external and internal) to the terrestrial plants were evaluated by estimating the concentration of anthropogenic ( 137 Cs, 90 Sr) and natural radionuclides ( 238 U, 232 Th and 40 K) in the plant leaves and by measuring the external gamma radiation due to different radionuclide. The soil and vegetation sample were collected from fifteen sampling locations around the different locations at Trombay. The samples were processed as per IAEA (International Atomic Energy Agency) protocol for the estimation of naturally occurring and anthropogenic radionuclides in soil and terrestrial plants. The gamma emitting radionuclides were measured by high resolution gamma (HPGe) spectrometry system. Maximum exposure (external + internal) to the terrestrial plants was observed due to 232 Th while 238 U showed minimum exposure. The average value of radiation exposure to the terrestrial plants for 40 K, 137 Cs, 90 Sr, 238 U and 232 Th was 1555.2 ± 92.4, 691.2 ± 54.3, 2564.1 ± 534.9, 82.5 ±5.2, and 4419.6 ± 1165.5 μGy/y respectively. The radiation exposure (external + internal ) to the terrestrial plants due to all radionuclides was found within the permissible limits (i.e. 10 mGy/d) as per recommended by the United States, Department of Energy (DOE). (author)

  20. Dose measurements in dental radiology using thermoluminescent dosimetry

    International Nuclear Information System (INIS)

    Chiara, Ana Claudia M. de; Costa, Alessandro M.; Pardini, Luiz Carlos

    2009-01-01

    The aim of this work was the implementation of a code of practice for dosimetry in dental radiology using the technique of thermoluminescent dosimetry. General principles for the use of thermoluminescent dosimeters were followed. The irradiations were performed using ten X-ray equipment for intra-oral radiography and an X-ray equipment for panoramic radiography. The incident air kerma was evaluated for five different exposure times used in clinical practice for intra-oral radiographs. Using a backscatter factor of 1.2, it was observed that approximately 40% of the entrance skin dose values found for intra-oral radiographs are above the diagnostic reference level recommended in national regulation. Different configurations of voltage and current were used representing the exposure as a child, woman and man for panoramic radiographs. The results obtained for the air kerma area product were respectively 53.3 +- 5.2 mGy.cm 2 , 101.5 +- 9.5 mGy.cm 2 and 116.8 +- 10.4 mGy.cm 2 . The use of thermoluminescent dosimetry requires several procedures before a result is recorded. The use of dosimeters with ionization chambers or semiconductors provides a simple and robust method for routine measurements. However, the use of thermoluminescent dosimetry can be of great value to large-scale surveys to establish diagnostic reference levels. (author)

  1. Radiological Impact Assessment in Disposal of Treated Sludge

    International Nuclear Information System (INIS)

    Khairuddin Mohamad Kontol; Ismail Sulaiman; Faizal Azrin Abdul Razalim

    2015-01-01

    Sludge and scales produced during oil and gas production contain enhanced naturally occurring radioactive material (NORM). Sludge and scales are under the jurisdiction of Department of Environment (DOE) and also Atomic Energy Licensing Board (AELB). AELB has issued a guideline regarding the disposal of sludge and scales as in its guideline (LEM/TEK/30 SEM.2, 1996). In this guideline, Radiological Impact Assessment (RIA) should be carried out on all proposed disposals and has to demonstrate that no member of public will be exposed to more than 1 mSv/y. This paper presented RIA analysis using RESRAD computer code for the disposal of treated sludge. RESRAD (RESidual RADioactive) developed by Argonne National Laboratory is to estimate radiation doses and risks from residual radioactive materials. The dose received by the member of public is found to be well below the stipulated limit. (author)

  2. Radiological assessment of private water supplies in Dolgellau, North Wales

    International Nuclear Information System (INIS)

    Green, D.; McReddie, R.; Holland, B.

    1993-01-01

    Water samples from 100 private water supplies in the Meirionnydd District Council area of Dolgellau, North Wales have been analysed for natural and artificial radionuclides and the elements Calcium and Strontium. In addition 20 of the 100 supplies were specifically sampled for the measurement of radon-222. Of the 100 supplies tested all total alpha and beta values were within the WHO guideline values. An assessment of the radiological significance of the analytical data has been carried out by calculating the committed effective dose equivalent to a hypothetical critical group which would arise from the consumption of water during a single year. The maximum adult annual committed effective dose equivalent for artificial and total radionuclides measured during this programme of monitoring was found to be 3.2 and 560 μSv, respectively. (author)

  3. The Bristol Radiology Report Assessment Tool (BRRAT): developing a workplace-based assessment tool for radiology reporting skills.

    Science.gov (United States)

    Wallis, A; Edey, A; Prothero, D; McCoubrie, P

    2013-11-01

    To review the development of a workplace-based assessment tool to assess the quality of written radiology reports and assess its reliability, feasibility, and validity. A comprehensive literature review and rigorous Delphi study enabled the development of the Bristol Radiology Report Assessment Tool (BRRAT), which consists of 19 questions and a global assessment score. Three assessors applied the assessment tool to 240 radiology reports provided by 24 radiology trainees. The reliability coefficient for the 19 questions was 0.79 and the equivalent coefficient for the global assessment scores was 0.67. Generalizability coefficients demonstrate that higher numbers of assessors and assessments are needed to reach acceptable levels of reliability for summative assessments due to assessor subjectivity. The study methodology gives good validity and strong foundation in best-practice. The assessment tool developed for radiology reporting is reliable and most suited to formative assessments. Copyright © 2013 The Royal College of Radiologists. Published by Elsevier Ltd. All rights reserved.

  4. The Bristol Radiology Report Assessment Tool (BRRAT): Developing a workplace-based assessment tool for radiology reporting skills

    International Nuclear Information System (INIS)

    Wallis, A.; Edey, A.; Prothero, D.; McCoubrie, P.

    2013-01-01

    Aim: To review the development of a workplace-based assessment tool to assess the quality of written radiology reports and assess its reliability, feasibility, and validity. Materials and methods: A comprehensive literature review and rigorous Delphi study enabled the development of the Bristol Radiology Report Assessment Tool (BRRAT), which consists of 19 questions and a global assessment score. Three assessors applied the assessment tool to 240 radiology reports provided by 24 radiology trainees. Results: The reliability coefficient for the 19 questions was 0.79 and the equivalent coefficient for the global assessment scores was 0.67. Generalizability coefficients demonstrate that higher numbers of assessors and assessments are needed to reach acceptable levels of reliability for summative assessments due to assessor subjectivity. Conclusion: The study methodology gives good validity and strong foundation in best-practice. The assessment tool developed for radiology reporting is reliable and most suited to formative assessments

  5. Radiological assessment of an area with uranium residual material

    International Nuclear Information System (INIS)

    Perez-Sanchez, Danyl; Cancio, David; Alvarez, Alicia

    2008-01-01

    As a result of a pilot project developed at the old Spanish 'Junta de Energia Nuclear' to extract uranium from ores, tailings materials were generated. Most of these residual materials were sent back to different uranium mines, but a small amount of it was mixed with conventional building materials and deposited near the old plant until the surrounding ground was flattened. The affected land is included in an area under institutional control and used as recreational area. At the time of processing, uranium isotopes were separated but other radionuclides of the uranium decays series as 230 Th, 226 Ra and daughters remain in the residue. Recently, the analyses of samples taken at different ground's depths confirm their presence. This paper presents the methodology used to calculate the derived concentration level to ensure the reference dose level of 0.1 mSv y-1 used as radiological criteria. In this study, a radiological impact assessment was performed modelling the area as recreational scenario. The modelization study was carried out with the code RESRAD considering as exposure pathways, external irradiation, inadvertent ingestion of soil, inhalation of resuspended particles, and inhalation of outdoor radon ( 222 Rn). As result was concluded that, if the concentration of 226 Ra in the first 15 cm of soil is lower than, 0.34 Bq g-1 , the dose would not exceed the reference dose. Applying this value as a derived concentration level and comparing with the results of measurements on the ground, some areas with a concentration of activity slightly higher than latter were found. In these zones the remediation proposal has been to cover with a layer of 15 cm of clean material. This action represents a reduction of 85% of the dose and ensures compliance with the reference dose. (author)

  6. The Generalised Ecosystem Modelling Approach in Radiological Assessment

    International Nuclear Information System (INIS)

    Klos, Richard

    2008-03-01

    An independent modelling capability is required by SSI in order to evaluate dose assessments carried out in Sweden by, amongst others, SKB. The main focus is the evaluation of the long-term radiological safety of radioactive waste repositories for both spent fuel and low-level radioactive waste. To meet the requirement for an independent modelling tool for use in biosphere dose assessments, SSI through its modelling team CLIMB commissioned the development of a new model in 2004, a project to produce an integrated model of radionuclides in the landscape. The generalised ecosystem modelling approach (GEMA) is the result. GEMA is a modular system of compartments representing the surface environment. It can be configured, through water and solid material fluxes, to represent local details in the range of ecosystem types found in the past, present and future Swedish landscapes. The approach is generic but fine tuning can be carried out using local details of the surface drainage system. The modular nature of the modelling approach means that GEMA modules can be linked to represent large scale surface drainage features over an extended domain in the landscape. System change can also be managed in GEMA, allowing a flexible and comprehensive model of the evolving landscape to be constructed. Environmental concentrations of radionuclides can be calculated and the GEMA dose pathway model provides a means of evaluating the radiological impact of radionuclide release to the surface environment. This document sets out the philosophy and details of GEMA and illustrates the functioning of the model with a range of examples featuring the recent CLIMB review of SKB's SR-Can assessment

  7. The Generalised Ecosystem Modelling Approach in Radiological Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Klos, Richard

    2008-03-15

    An independent modelling capability is required by SSI in order to evaluate dose assessments carried out in Sweden by, amongst others, SKB. The main focus is the evaluation of the long-term radiological safety of radioactive waste repositories for both spent fuel and low-level radioactive waste. To meet the requirement for an independent modelling tool for use in biosphere dose assessments, SSI through its modelling team CLIMB commissioned the development of a new model in 2004, a project to produce an integrated model of radionuclides in the landscape. The generalised ecosystem modelling approach (GEMA) is the result. GEMA is a modular system of compartments representing the surface environment. It can be configured, through water and solid material fluxes, to represent local details in the range of ecosystem types found in the past, present and future Swedish landscapes. The approach is generic but fine tuning can be carried out using local details of the surface drainage system. The modular nature of the modelling approach means that GEMA modules can be linked to represent large scale surface drainage features over an extended domain in the landscape. System change can also be managed in GEMA, allowing a flexible and comprehensive model of the evolving landscape to be constructed. Environmental concentrations of radionuclides can be calculated and the GEMA dose pathway model provides a means of evaluating the radiological impact of radionuclide release to the surface environment. This document sets out the philosophy and details of GEMA and illustrates the functioning of the model with a range of examples featuring the recent CLIMB review of SKB's SR-Can assessment

  8. Assessing radiologic risk for population due to human activities

    International Nuclear Information System (INIS)

    Toma, Al.; Dulama, C.; Dobrin, R.; Hirica, O.

    2002-01-01

    The most important factor in assessing radiologic risk is ensuring scientific means for evaluation of the radioactive release impact upon humans and organisms. To evaluate quantitatively this impact not only knowledge of radioactivity distribution in these dynamical systems is necessary but also understanding the transfer mechanisms between ecosystem components is needed. Thus a complete radioecologic study appear to be very complex and needs defining the source term, dynamic description of radionuclides behavior in the ecosystem, estimation of radiation doses in the major components of the ecosystem and finally the effects of radiation doses upon different parts of the systems. A diagram of the steps implied in evaluation of the effects due to radioactive effluent release in the environment is presented and discussed. The following steps are described: - identification of radioactive sources, as well as their input rate. Presence of noxious materials such as heavy metals or some organic compounds should be taken into account to assess the synergetic or antagonistic interactions; - determination of space-time distribution of release radionuclides; - estimation of dose rates and radiation exposure of population; - estimation of radiation dose effects upon individuals, population and ecosystems. This fourth step implies: experimental field or laboratory studies to determine the somatic/genetic response to radiation as a function of the exposure dose; following-up and interpretation of the organism response to dose or dose rates in terms of radiation-induce changes in the population life cycles; forecasting the irradiation effects upon population or communities within environment. Finally, this evaluation is completed by the decision making process implying a society acceptance of the forecast and/or observed effects

  9. Radiological services pact relies on teamwork and experience [dose management

    International Nuclear Information System (INIS)

    Cruden, D.S.

    1988-01-01

    Virginia Power has entered into a radiological service agreement with Westinghouse. The contract commits Westinghouse to work in partnership with Virginia Power to improve performance in the areas of radiological protection, decontamination, ALARA, and radioactive waste management. It is expected that the agreement will solve the problems caused by the shortage of qualified contractor personnel during scheduled outages. (U.K.)

  10. Radiological assessment of the town of Edgemont

    International Nuclear Information System (INIS)

    Jackson, P.O.; Thomas, V.W.; Young, J.A.

    1985-01-01

    Congress, in 1980, gave the Nuclear Regulatory Commission (NRC) the responsibility to coordinate and conduct a monitoring, engineering assessment, and remedial cleanup program in Edgemont, South Dakota. The Congressional intent was to locate public properties in Edgemont that had been contaminated by radioactive materials from a local uranium mill, and to clean up those properties. Because the Atomic Energy Act of 1954 gave NRC the authority to monitor for contamination but not to clean up contamination, Congress later assigned the remedial cleanup responsibility to the Department of Energy (DOE). NRC, through Battelle Pacific Northwest Laboratory (PNL), conducted a radiological survey of 96% of the properties in Edgemont and vicinity during the time period of September 1980 through April 1984. (Out of 976 total properties, 941 were surveyed.) The strategy of the survey was to screen properties for the possible presence of contamination by using short- and long-term radon progeny measurements, indoor and outdoor gamma exposure rate measurements, and soil radium-226 measurements. Properties that failed the screening surveys were measured more extensively to determine whether the elevated readings were due to residual radioactive materials from the uranium mill. This report contains the historical perspective of the Edgemont survey, explains the development and modifications of survey protocols, examines the problems encountered during the survey, and lists a summary of the results. The report also presents conclusions about the effectiveness of the survey techniques and about the rationale of a comprehensive survey of a whole community. The appendices section of this report contains all the protocols, a list of all the properties showing survey results for each, and reports on special studies conducted during the survey. These special studies contain many valuable insights that may prove beneficial to future radiological assessment surveys

  11. Dose and dose-rate effects of ionizing radiation: a discussion in the light of radiological protection

    Energy Technology Data Exchange (ETDEWEB)

    Ruehm, Werner [Helmholtz Zentrum Muenchen, German Research Center for Environmental Health, Institute of Radiation Protection, Neuherberg (Germany); Woloschak, Gayle E. [Northwestern University, Department of Radiation Oncology, Feinberg School of Medicine, Chicago, IL (United States); Shore, Roy E. [Radiation Effects Research Foundation (RERF), Hiroshima City (Japan); Azizova, Tamara V. [Southern Urals Biophysics Institute (SUBI), Ozyorsk, Chelyabinsk Region (Russian Federation); Grosche, Bernd [Federal Office for Radiation Protection, Oberschleissheim (Germany); Niwa, Ohtsura [Fukushima Medical University, Fukushima (Japan); Akiba, Suminori [Kagoshima University Graduate School of Medical and Dental Sciences, Department of Epidemiology and Preventive Medicine, Kagoshima City (Japan); Ono, Tetsuya [Institute for Environmental Sciences, Rokkasho, Aomori-ken (Japan); Suzuki, Keiji [Nagasaki University, Department of Radiation Medical Sciences, Atomic Bomb Disease Institute, Nagasaki (Japan); Iwasaki, Toshiyasu [Central Research Institute of Electric Power Industry (CRIEPI), Radiation Safety Research Center, Nuclear Technology Research Laboratory, Tokyo (Japan); Ban, Nobuhiko [Tokyo Healthcare University, Faculty of Nursing, Tokyo (Japan); Kai, Michiaki [Oita University of Nursing and Health Sciences, Department of Environmental Health Science, Oita (Japan); Clement, Christopher H.; Hamada, Nobuyuki [International Commission on Radiological Protection (ICRP), PO Box 1046, Ottawa, ON (Canada); Bouffler, Simon [Public Health England (PHE), Centre for Radiation, Chemical and Environmental Hazards, Chilton, Didcot (United Kingdom); Toma, Hideki [JAPAN NUS Co., Ltd. (JANUS), Tokyo (Japan)

    2015-11-15

    The biological effects on humans of low-dose and low-dose-rate exposures to ionizing radiation have always been of major interest. The most recent concept as suggested by the International Commission on Radiological Protection (ICRP) is to extrapolate existing epidemiological data at high doses and dose rates down to low doses and low dose rates relevant to radiological protection, using the so-called dose and dose-rate effectiveness factor (DDREF). The present paper summarizes what was presented and discussed by experts from ICRP and Japan at a dedicated workshop on this topic held in May 2015 in Kyoto, Japan. This paper describes the historical development of the DDREF concept in light of emerging scientific evidence on dose and dose-rate effects, summarizes the conclusions recently drawn by a number of international organizations (e.g., BEIR VII, ICRP, SSK, UNSCEAR, and WHO), mentions current scientific efforts to obtain more data on low-dose and low-dose-rate effects at molecular, cellular, animal and human levels, and discusses future options that could be useful to improve and optimize the DDREF concept for the purpose of radiological protection. (orig.)

  12. Radiologic imaging in cystic fibrosis: cumulative effective dose and changing trends over 2 decades.

    LENUS (Irish Health Repository)

    O'Connell, Oisin J

    2012-06-01

    With the increasing life expectancy for patients with cystic fibrosis (CF), and a known predisposition to certain cancers, cumulative radiation exposure from radiologic imaging is of increasing significance. This study explores the estimated cumulative effective radiation dose over a 17-year period from radiologic procedures and changing trends of imaging modalities over this period.

  13. Overview of double dosimetry procedures for the determination of the effective dose to the interventional radiology staff

    International Nuclear Information System (INIS)

    Jaervinen, H.; Buls, N.; Clerinx, P.; Jansen, J.; Miljanic, S.; Nikodemova, D.; Ranogajec-Komor, M.; D'Errico, F.

    2008-01-01

    In interventional radiology, for an accurate determination of effective dose to the staff, measurements with two dosemeters have been recommended, one located above and one under the protective apron. Such 'double dosimetry' practices and the algorithms used for the determination of effective dose were reviewed in this study by circulating a questionnaire and by an extensive literature search. The results indicated that regulations for double dosimetry almost do not exist and there is no firm consensus on the most suitable calculation algorithms. The calculation of effective dose is mainly based on the single dosemeter measurements, in which either personal dose equivalent, directly, (dosemeter below the apron) or a fraction of personal dose equivalent (dosemeter above the apron) is taken as an assessment of effective dose. The most recent studies suggest that there might not be just one double dosimetry algorithm that would be optimum for all interventional radiology procedures. Further investigations in several critical configurations of interventional radiology procedures are needed to assess the suitability of the proposed algorithms. (authors)

  14. Radiological risk assessment of a radioactively contaminated site

    International Nuclear Information System (INIS)

    Devgun, J.S.

    1990-01-01

    A limited-scope preliminary assessment of radiological risk has been conducted at a radioactively contaminated site under current site use conditions and based on the available preliminary radiological characterization data for the site. The assessment provides useful input to the remedial action planning for the site. 8 refs., 1 fig., 2 tabs

  15. Radioactive Waste Management Complex low-level waste radiological performance assessment

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, S.J.; Rood, A.S.; Magnuson, S.O.; Sussman, M.E.; Bhatt, R.N.

    1994-04-01

    This report documents the projected radiological dose impacts associated with the disposal of radioactive low-level waste at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. This radiological performance assessment was conducted to evaluate compliance with applicable radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the public and the environment. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses were made for both offsite receptors and individuals inadvertently intruding onto the site after closure. In addition, uncertainty and sensitivity analyses were performed. The results of the analyses indicate compliance with established radiological criteria and provide reasonable assurance that public health and safety will be protected.

  16. Radioactive Waste Management Complex low-level waste radiological performance assessment

    International Nuclear Information System (INIS)

    Maheras, S.J.; Rood, A.S.; Magnuson, S.O.; Sussman, M.E.; Bhatt, R.N.

    1994-04-01

    This report documents the projected radiological dose impacts associated with the disposal of radioactive low-level waste at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. This radiological performance assessment was conducted to evaluate compliance with applicable radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the public and the environment. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses were made for both offsite receptors and individuals inadvertently intruding onto the site after closure. In addition, uncertainty and sensitivity analyses were performed. The results of the analyses indicate compliance with established radiological criteria and provide reasonable assurance that public health and safety will be protected

  17. Radiological Safety Assessment of Transporting Radioactive Wastes to the Gyeongju Disposal Facility in Korea

    Directory of Open Access Journals (Sweden)

    Jongtae Jeong

    2016-12-01

    Full Text Available A radiological safety assessment study was performed for the transportation of low level radioactive wastes which are temporarily stored in Korea Atomic Energy Research Institute (KAERI, Daejeon, Korea. We considered two kinds of wastes: (1 operation wastes generated from the routine operation of facilities; and (2 decommissioning wastes generated from the decommissioning of a research reactor in KAERI. The important part of the radiological safety assessment is related to the exposure dose assessment for the incident-free (normal transportation of wastes, i.e., the radiation exposure of transport personnel, radiation workers for loading and unloading of radioactive waste drums, and the general public. The effective doses were estimated based on the detailed information on the transportation plan and on the radiological characteristics of waste packages. We also estimated radiological risks and the effective doses for the general public resulting from accidents such as an impact and a fire caused by the impact during the transportation. According to the results, the effective doses for transport personnel, radiation workers, and the general public are far below the regulatory limits. Therefore, we can secure safety from the viewpoint of radiological safety for all situations during the transportation of radioactive wastes which have been stored temporarily in KAERI.

  18. Radiological safety assessment of transporting radioactive waste to the Gyeongju disposal facility in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Jong Tae; Baik, Min Hoon; Kang, Mun Ja; Ahn, Hong Joo; Hwang, Doo Seong; Hong, Dae Seok; Jeong, Yong Hwan; Kim, Kyung Su [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-12-15

    A radiological safety assessment study was performed for the transportation of low level radioactive wastes which are temporarily stored in Korea Atomic Energy Research Institute (KAERI), Daejeon, Korea. We considered two kinds of wastes: (1) operation wastes generated from the routine operation of facilities; and (2) decommissioning wastes generated from the decommissioning of a research reactor in KAERI. The important part of the radiological safety assessment is related to the exposure dose assessment for the incident-free (normal) transportation of wastes, i.e., the radiation exposure of transport personnel, radiation workers for loading and unloading of radioactive waste drums, and the general public. The effective doses were estimated based on the detailed information on the transportation plan and on the radiological characteristics of waste packages. We also estimated radiological risks and the effective doses for the general public resulting from accidents such as an impact and a fire caused by the impact during the transportation. According to the results, the effective doses for transport personnel, radiation workers, and the general public are far below the regulatory limits. Therefore, we can secure safety from the viewpoint of radiological safety for all situations during the transportation of radioactive wastes which have been stored temporarily in KAERI.

  19. Assessment of radiological releases to the environment from a fusion reactor power plant

    International Nuclear Information System (INIS)

    Shank, K.E.; Oakes, T.W.; Easterly, C.E.

    1978-05-01

    This report summarizes the expected tritium and activation-product inventories and presents an assessment of the potential radiological releases from a fusion reactor power plant, hypothetically located at the Oak Ridge National Laboratory. Routine tritium releases and the resulting dose assessment are discussed. Uncertainties associated with the conversion of tritium gas to tritium oxide and the global tritium cycling are evaluated. The difficulties of estimating releases of activated materials and the subsequent dose commitment are reviewed

  20. Current situation of doses delivered to the patients in the field of dental radiology

    International Nuclear Information System (INIS)

    Baechler, S.; Monnin, P.; Aroua, A.; Valley, J.F.; Verdun, F.R.; Perrier, M.

    2006-01-01

    The purpose of this paper is to present an overview of the doses delivered to the patients in the field of dental radiology. The technology progress in medical imaging will be discussed from a dose perspective. In this work, patient dosimetry has been performed for intra-oral, panoramic and CT dental examinations. Doses were estimated using appropriate dosimetric indicators such as the entrance surface kerma (ESK) and the kerma area product (KAP). These indicators are easily measurable and enable to estimate the effective dose for a standard patient. KAP values were measured for two intra-oral systems using D and E/F speed dental films, as well as a digital system based on the CCD technology. In addition, the KAP was measured on three ortho-pan-tomograms (OPGs) of various generations. Finally, in order to assess the dose delivered during dental implants planning, the kerma length product (KLP) and the computed tomography dose index (CTDI W ) were determined for a CT scanner using the Dentascan protocol and a new DVT (Digital Volume Tomography) dedicated system. Using E/F speed instead of D speed films allowed to educe the KAP by a factor of 2 without significant loss of image quality. A further dose reduction by a factor of 6 was possible with digital systems but with an important degradation of the spatial resolution (variation of the MTF at 50% from 13 mm -1 to 5 mm -1 ). KAP measurements on OPGs showed that old systems delivered doses three times higher than a more recent devices. The new dedicated tomographic system enabled a reduction of the patient dose by a factor of 18 when compared with the Dentascan CT system. (author)

  1. Comparative analysis of dose levels to patients in radiological procedures guided by fluoroscopy

    International Nuclear Information System (INIS)

    Gomez, Pablo Luis; Fernandez, Manuel; Ramos, Julio A.; Delgado, Jose Miguel; Cons, Nestor

    2013-01-01

    This work presents the comparative data of the dose indicators for patient in radiological processes with respect to the values published in the ICRP document. It is analyzed the need for different strategies to communicate to different specialists mechanisms to optimize the radiation beginning with practice by training of second degree level in radiological protection and then, working with them the basics of equipment management to reduce doses without detriment to the welfare purpose

  2. Consultative exercise on dose assessments.

    Science.gov (United States)

    Bridges, B A; Parker, T; Simmonds, J R; Sumner, D

    2001-06-01

    A summary is given of a meeting held at Sussex University, UK, in October 2000, which allowed the exchange of ideas on methods of assessment of dose to the public arising from potential authorised radioactive discharges from nuclear sites in the UK. Representatives of groups with an interest in dose assessments were invited, and hence the meeting was called the Consultative Exercise on Dose Assessments (CEDA). Although initiated and funded by the Food Standards Agency, its organisation, and the writing of the report, were overseen by an independent Chairman and Steering Group. The report contains recommendations for improvement in co-ordination between different agencies involved in assessments, on method development and on the presentation of data on assessments. These have been prepared by the Steering Group, and will be taken forward by the Food Standards Agency and other agencies in the UK. The recommendations are included in this memorandum.

  3. Product kerma air area and effective dose in dental radiology; Produto kerma no ar-area e dose efetiva em radiodiagnostico odontologico

    Energy Technology Data Exchange (ETDEWEB)

    Mauro, Rodrigo A.P.; Souza, M. Daiane M.; Costa, Alessandro M. [Universidade de Sao Paulo (USP), Ribeirao Preto (USP), SP (Brazil). Faculdade de Filosofia Ciencias e Letras

    2016-07-01

    The main purpose of patient dosimetry in diagnostic radiology is to determine dosimetric quantities for the establishment and use of reference levels and comparative risk assessment. The use of the air kerma-area product, P{sub KA}, has been suggested in dental radiology, as this quantity is more closely related to risk. The aim of this study was to perform a preliminary survey of P{sub KA} and effective dose in different types of dental examinations. The future perspective is a large-scale survey for the establishment and use of diagnostic reference levels in dentistry in Brazil. (author)

  4. Product kerma air area and effective dose in dental radiology; Produto kerma no ar area e dose efetiva em radiodiagnostico odontologico

    Energy Technology Data Exchange (ETDEWEB)

    Mauro, Rodrigo A.P.; Souza, Daiane M.; Costa, Alessandro M., E-mail: rodrigomauro@usp.br [Universidade de Sao Paulo (USP), Ribeirao Preto, SP (Brazil). Faculdade de Filosofia Ciencias e Letras

    2016-07-01

    The main purpose of patient dosimetry in diagnostic radiology is to determine dosimetric quantities for the establishment and use of reference levels and comparative risk assessment. The use of the air kerma-area product, P{sub KA}, has been suggested in dental radiology, as this quantity is more closely related to risk. The aim of this study was to perform a preliminary survey of P{sub KA} and effective dose in different types of dental examinations. The future perspective is a large-scale survey for the establishment and use of diagnostic reference levels in dentistry in Brazil. (author)

  5. The role of the dose-area product in the determination of doses to patients in diagnostic radiology. Experiences and current understanding

    International Nuclear Information System (INIS)

    Maier, W.

    1995-01-01

    Described are systems and procedures developed to assess the radiation exposure of patients. They may at the same time be used to reduce the doses to patients undergoing radiological examinations. As the digitalization of state-of-the-art X-ray equipments permits the technical data of any radiographic procedure to be retrieved, it is requested that these are fed into appropriate data systems so that information about any inadequate strategies or technical misfunctions would be available in due course. This request implies the general requirement of an automatic documentation of data relevant to radiological protection. (orig.) [de

  6. Radiation dose evaluation in patients submitted to conventional radiological examinations; Avaliacoes de doses de radiacao em pacientes submetidos a exames radiologicos convencionais

    Energy Technology Data Exchange (ETDEWEB)

    Tilly, Junior, Joao G

    1997-07-01

    This work presents the results of the evaluation of radiation dose delivered to the patients undergoing conventional radiological procedures. Based in the realized measurement some indicators are settled to quantitative appraisal of the radiological protection conditions offered to the population. Data assessment was done in the county of Curitiba, in Parana State, Brazil, from 12/95 to 04/96, in ten rooms of three different institutions, under 101 patients, adults with 70 {+-} 10 kg, during real examinations of chest PA, chest LAT and abdomen AP. (author)

  7. Extremity doses of medical staff involved in interventional radiology and cardiology: Correlations and annual doses (hands and legs)

    International Nuclear Information System (INIS)

    Krim, S.; Brodecki, M.; Carinou, E.; Donadille, L.; Jankowski, J.; Koukorava, C.; Dominiek, J.; Nikodemova, D.; Ruiz-Lopez, N.; Sans-Merce, M.; Struelens, L.; Vanhavere, F.

    2011-01-01

    An intensive measurement campaign was launched in different hospitals in Europe within work package 1 of the ORAMED project (Optimization of RAdiation protection for MEDical staff). Its main objective was to obtain a set of standardized data on extremity and eye lens doses for staff in interventional radiology (IR) and cardiology (IC) and to optimize staff protection. The monitored procedures were divided in three main categories: cardiac, general angiography and endoscopic retrograde cholangio-pancreatography(ERCP) procedures. Using a common measurement protocol, information such as the protective equipment used (lead table curtain, transparent lead glass ceiling screen, patient shielding, whole body shielding or special cabin etc.) as well as Kerma Area Product (KAP) values and access of the catheter were recorded. This study was performed with a final database of more than 1300 procedures performed in 34 European hospitals. Its objectives were firstly to determine if the measured extremity doses could be correlated to the KAP values; secondly to check if the doses to the eyes could be linked to the doses to the hands (finger or wrist positions) and finally if the doses to the fingers could be estimated based on the doses to the wrists. General correlations were very difficult to find and their strength was mostly influenced by three main parameters: the X-ray tube configuration, the room collective radioprotective equipment and the access of the catheter. The KAP value can provide a simple mean to estimate the extremity doses of the operator given that it is assessed correctly for the operator when he is actually using the X-ray tube. Moreover, this study showed that the doses to the left finger are strongly correlated to the doses to the left wrist when no ceiling shield is used. It is also possible to estimate the doses to the eyes given the doses to the left finger or left wrist but the X-ray tube configuration and the access have to be considered. The annual

  8. Assessment of radiological protection systems among diagnostic radiology facilities in North East India.

    Science.gov (United States)

    Singh, Thokchom Dewan; Jayaraman, T; Arunkumar Sharma, B

    2017-03-01

    This study aims to assess the adequacy level of radiological protection systems available in the diagnostic radiology facilities located in three capital cities of North East (NE) India. It further attempts to understand, using a multi-disciplinary approach, how the safety codes/standards in diagnostic radiology framed by the Atomic Energy Regulatory Board (AERB) and the International Atomic Energy Agency (IAEA) to achieve adequate radiological protection in facilities, have been perceived, conceptualized, and applied accordingly in these facilities. About 30 diagnostic radiology facilities were randomly selected from three capitals of states in NE India; namely Imphal (Manipur), Shillong (Meghalaya) and Guwahati (Assam). A semi-structured questionnaire developed based on a multi-disciplinary approach was used for this study. It was observed that radiological practices undertaken in these facilities were not exactly in line with safety codes/standards in diagnostic radiology of the AERB and the IAEA. About 50% of the facilities had registered/licensed x-ray equipment with the AERB. More than 80% of the workers did not use radiation protective devices, although these devices were available in the facilities. About 85% of facilities had no institutional risk management system. About 70% of the facilities did not carry out periodic quality assurance testing of their x-ray equipment or surveys of radiation leakage around the x-ray room, and did not display radiation safety indicators in the x-ray rooms. Workers in these facilities exhibited low risk perception about the risks associated with these practices. The majority of diagnostic radiology facilities in NE India did not comply with the radiological safety codes/standards framed by the AERB and IAEA. The study found inadequate levels of radiological protection systems in the majority of facilities. This study suggests a need to establish firm measures that comply with the radiological safety codes/standards of the

  9. Efforts towards enhancing the quality of radiological services in Malaysia: review of patient dose surveys 1993-2007

    International Nuclear Information System (INIS)

    Hairuman, H.; Sapiin, B.; Muthuvelu, P.; Hatta, N.; Hambali, A.S.

    2008-01-01

    Full text: The Ministry of Health (MoH) Malaysia is continuously taking steps to improve the quality of radiological services provided by the public and private medical institutions. This is to ensure that optimum diagnostic information is obtained with the least exposure to patients as well as staff. Over the years, MOH has taken both administrative and legislative measures to enforce the various requirements under the Atomic Energy Licensing Act 1984. In order to further upgrade and enhance the quality, safety and efficacy of radiological services, implementation of the Quality Assurance Programme (QAP) has been made mandatory. Implementation of the QAP comprises certification of irradiating equipment, training of personnel (continuous professional education), film reject rate analysis and film auditing and assessment. All these particulars must be documented and submitted annually to the MoH in order to comply with licensing requirements. It is envisaged that with the implementation of QAP, the medical institutions will be able to institutionalise and internalise the culture of quality and safety in the applications of radiation in medicine. This implementation will indirectly result in reduction of dose to the patient and importantly in optimization the use of ionizing radiation in medicine. With the QAP in place a survey of doses to patient in 7 routine X-ray examinations was initiated in 1993 to provide a reference dose baseline in Malaysia. This was then followed by further dose surveys involving other modalities namely interventional radiology, mammography, adult chest and abdominal X-rays and computer tomography dose index (CTDI) for head and body phantom in CT scanner. The results of these dose surveys will be reviewed in this paper. The results of the mean entrance surface dose (ESD) (mGy) to patients in 7 routine X-ray examination done (1993 - 1995), the mean values of dose area product (DAP) (Gycm 2 ) for patient undergoing interventional radiology

  10. Assessment of radiological risks at the ATLAS experiment

    International Nuclear Information System (INIS)

    Zajacova, Z.

    2009-07-01

    the critical population group is 1:5 μSv. At the end, the argon activation was recalculated to cross-check the original activation data. The cross-check was done as a comparative study with six sets of cross sections. For most radionuclides the activities calculated with the different cross section sets vary within a factor of three, which is acceptable for the purpose of radiological impact assessment. The biggest variation was found in predicting the production of tritium, 31 Si and 38 S, none of which has a significant influence in terms of the radiological impact. Activation of air in the cavern and its radiological impact were assessed. The activities of 39 radionuclides were calculated and the activity in the air of the cavern was expressed in terms of the CA values of the Swiss legislation. The radiological impact from external exposure and inhalation of this air was derived from the definition of the CA values. A 30 minute intervention would result in an effective dose of about 0.7 μSv. (Author)

  11. Radiological endpoints relevant to ecological risk assessment

    International Nuclear Information System (INIS)

    Harrison, F.

    1997-01-01

    Because of the potential risk from radiation due to the releases of radionuclides from anthropogenic activities, considerable research was performed to determine for humans the levels of dose received, their responses to the doses and mechanisms of action of radioactivity on living matter. More recently, there is an increased interest in the effects of radioactivity on non-human species. There are differences in approach between risk assessment for humans and ecosystems. For protection of humans, the focus is the individual and the endpoint of primary concern is cancer induction. For protection of ecosystems, the focus is on population stability and the endpoint of concern is reproductive success for organisms important ecologically and economically. For these organisms, information is needed on their responses to irradiation and the potential impact of the doses absorbed on their reproductive success. Considerable information is available on the effects of radiation on organisms from different phyla and types of ecosystems. Databases useful for assessing risk from exposures of populations to radioactivity are the effects of irradiation on mortality, fertility and sterility, the latter two of which are important components of reproductive success. Data on radiation effects on mortality are available both from acute and chronic irradiation. In relation to radiation effects, reproductive success for a given population is related to a number of characteristics of the species, including inherent radiosensitivity of reproductive tissues and early life stages, processes occurring during gametogenesis, reproductive strategy and exposure history. The available data on acute and chronic radiation doses is reviewed for invertebrates, fishes and mammals. The information reviewed indicates that wide ranges in responses with species can be expected. Parameters that most likely contribute to inherent radiosensitivity are discussed. (author)

  12. Principles of the International Commission on Radiological Protection system of dose limitation

    International Nuclear Information System (INIS)

    Thorne, M.C.

    1987-01-01

    The formulation of a quantitative system of dose limitation based on ICRP principles of 'stochastic' and 'non-stochastic' effects requires that judgements be made on several factors including: relationships between radiation dose and the induction of deleterious effects for a variety of endpoints and radiation types; acceptable levels of risk for radiation workers and members of the public; and methods of assessing whether the cost of introducing protective measures is justified by the reduction in radiation detriment which they will provide. In the case of patients deliberately exposed to ionising radiations, the objectives of radiation protection differ somewhat from those applying to radiation workers and members of the public. For patients, risks and benefits relate to the same person and upper limits on acceptable risks may differ grossly from those appropriate to normal individuals. For these reasons, and because of its historical relationship with the International Congress of Radiology, the ICRP has given special consideration to radiation protection in medicine and has published reports on protection of the patient in diagnostic radiology and in radiation therapy. (author)

  13. Radiology Residents' Awareness about Ionizing Radiation Doses in Imaging Studies and Their Cancer Risk during Radiological Examinations

    Energy Technology Data Exchange (ETDEWEB)

    Goekce, Senem Divrik [I. Ikad Community Health Center, Health Directorate, Samsun (Turkmenistan); Gekce, Erkan [Samsun Maternity and Women' s Disease and Pediatrics Hospital, Samsun (Turkmenistan); Coskun, Melek [Faculty of Medicine, Ondokuz May' s University, Samsun (Turkmenistan)

    2012-03-15

    Imaging methods that use ionizing radiation have been more frequent in various medical fields with advances in imaging technology. The aim of our study was to make residents be aware of the radiation dose they are subjected to when they conduct radiological imaging methods, and of cancer risk. A total of 364 residents participated in this descriptive study which was conducted during the period between October, 2008 and January, 2009. The questionnaires were completed under strict control on a one-to-one basis from each department. A X{sup 2}-test was used for the evaluation of data obtained. Only 7% of residents correctly answered to the question about the ionizing radiation dose of a posteroanterior (PA) chest X-ray. The question asking about the equivalent number of PA chest X-rays to the ionizing dose of a brain CT was answered correctly by 24% of residents; the same question regarding abdominal CT was answered correctly by 16% of residents, thorax CT by 16%, thyroid scintigraphy by 15%, intravenous pyelography by 9%, and lumbar spine radiography by 2%. The risk of developing a cancer throughout lifetime by a brain and abdominal CT were 33% and 28%, respectively. Radiologic residents should have updated knowledge about radiation dose content and attendant cancer risks of various radiological imaging methods during both basic medical training period and following practice period.

  14. Radiology Residents' Awareness about Ionizing Radiation Doses in Imaging Studies and Their Cancer Risk during Radiological Examinations

    Science.gov (United States)

    Divrik Gökçe, Senem; Coşkun, Melek

    2012-01-01

    Objective Imaging methods that use ionizing radiation have been more frequent in various medical fields with advances in imaging technology. The aim of our study was to make residents be aware of the radiation dose they are subjected to when they conduct radiological imaging methods, and of cancer risk. Materials and Methods A total of 364 residents participated in this descriptive study which was conducted during the period between October, 2008 and January, 2009. The questionnaires were completed under strict control on a one-to-one basis from each department. A χ2-test was used for the evaluation of data obtained. Results Only 7% of residents correctly answered to the question about the ionizing radiation dose of a posteroanterior (PA) chest X-ray. The question asking about the equivalent number of PA chest X-rays to the ionizing dose of a brain CT was answered correctly by 24% of residents; the same question regarding abdominal CT was answered correctly by 16% of residents, thorax CT by 16%, thyroid scintigraphy by 15%, intravenous pyelography by 9%, and lumbar spine radiography by 2%. The risk of developing a cancer throughout lifetime by a brain and abdominal CT were 33% and 28%, respectively. Conclusion Radiologic residents should have updated knowledge about radiation dose content and attendant cancer risks of various radiological imaging methods during both basic medical training period and following practice period. PMID:22438688

  15. Radiology Residents' Awareness about Ionizing Radiation Doses in Imaging Studies and Their Cancer Risk during Radiological Examinations

    International Nuclear Information System (INIS)

    Goekce, Senem Divrik; Gekce, Erkan; Coskun, Melek

    2012-01-01

    Imaging methods that use ionizing radiation have been more frequent in various medical fields with advances in imaging technology. The aim of our study was to make residents be aware of the radiation dose they are subjected to when they conduct radiological imaging methods, and of cancer risk. A total of 364 residents participated in this descriptive study which was conducted during the period between October, 2008 and January, 2009. The questionnaires were completed under strict control on a one-to-one basis from each department. A X 2 -test was used for the evaluation of data obtained. Only 7% of residents correctly answered to the question about the ionizing radiation dose of a posteroanterior (PA) chest X-ray. The question asking about the equivalent number of PA chest X-rays to the ionizing dose of a brain CT was answered correctly by 24% of residents; the same question regarding abdominal CT was answered correctly by 16% of residents, thorax CT by 16%, thyroid scintigraphy by 15%, intravenous pyelography by 9%, and lumbar spine radiography by 2%. The risk of developing a cancer throughout lifetime by a brain and abdominal CT were 33% and 28%, respectively. Radiologic residents should have updated knowledge about radiation dose content and attendant cancer risks of various radiological imaging methods during both basic medical training period and following practice period.

  16. Preliminary radiological assessments of near-surface low-level radioactive waste repositories

    International Nuclear Information System (INIS)

    Sumerling, T.J.; Nancarrow, D.J.

    1988-08-01

    This report summarises preliminary assessments of post-closure radiological impact of LLW repositories at four sites previously under investigation by UK Nirex Ltd. The objectives of the assessments were: to demonstrate a methodology for site specific assessments, to identify important information requirements for detailed assessments; to identify methodological and research requirements. Doses and risks due to groundwater pathways, human intrusion, gaseous release and natural environmental change are estimated. (author)

  17. Absorbed Doses to Embryo from Intravenous Urography at Selected Radiological Departments in Slovakia

    International Nuclear Information System (INIS)

    Karkus, R.; Nikodemova, D.; Horvathova, M.

    2003-01-01

    Actual legislation used in radiological protection requires quality assurance program for decreasing radiation load of patients from radiological examinations. The information about irradiation of pregnant women is very important, because the embryo is more radiosensitive as adult organism. On the basis of absence of unified calculations or measurements of absorbed doses to embryo from various radiological examinations in Slovakia we present in this study the values of absorbed doses to embryo from intravenous urography at selected radiological departments in Slovakia. Absorbed doses to embryo were obtained by measurement and calculation using the simulation of irradiation of pregnant woman by intravenous urography. The results of our study indicate, that absorbed doses to embryo were at various radiological departments considerably different, depending on type of X-ray machine and different settings of technical parameters of X-ray machine. In accordance with worldwide trend it is necessary to decrease radiation load of patients as low as possible level. Differences in radiation load between radiological departments indicate, that it is necessary to continue in solving of this problem and perform measurements and calculations of absorbed doses to embryo at different types of X-ray machines and at different examinations, where the embryo is in direct beam of X-ray. (author)

  18. Radiological assessment of dam water and sediments for natural ...

    African Journals Online (AJOL)

    Radiological assessment of dam water and sediments for natural radioactivity and its overall health detriments. ... No artificial gamma emitting radionuclide was detected in the samples. The projected ... However, the chances of radiological hazard to the health of human from radioactivity in the soil were generally low.

  19. Multicentre Assessment of Radiology Request Form Completion in ...

    African Journals Online (AJOL)

    An important element in the multidisciplinary approach to patient management is communications among clinicians. As most of the patients attending any hospital have to go through the department of radiology, the pattern and attitude of clinicians to the completion of radiology request forms was assessed in three teaching ...

  20. Radiological assessment of decommissioned nuclear facilities

    International Nuclear Information System (INIS)

    Dickson, H.W.; Cottrell, W.D.

    1976-01-01

    A radiological survey of the former Middlesex Sampling Plant, Middlesex, New Jersey, has been completed. The surveyed property served as a uranium ore sampling plant during the 1940's and early 1950's. It was released for unrestricted use in 1967 following a radiological survey by the Atomic Energy Commission and is now a reserve training center for the U. S. Marine Sixth Motor Transport Battalion. The present survey was undertaken to determine whether the existing radiological status of the property is consistent with current health standards and radiation protection practices. The radiological survey included measurement of residual alpha, beta, and gamma contamination levels, radon and radon daughter concentrations in buildings, external gamma radiation levels on the site and on adjacent property, and radium concentrations in soil on the site and on adjacent property

  1. Radiology

    International Nuclear Information System (INIS)

    Bigot, J.M.; Moreau, J.F.; Nahum, H.; Bellet, M.

    1990-01-01

    The 17th International Congress of Radiology was conducted in two separate scientific sessions, one for radiodiagnosis and one for radiation oncology. Topics covered are: Radiobiology -radioprotection; imaging and data processing; contrast media; MRI; nuclear medicine; radiology and disasters; radiology of tropical diseases; cardiovascular radiology; interventional radiology; imaging of trauma; imaging of chest, gastro-intestinal tract, breast and genito-urinary tract; imaging in gynecology;imaging in oncology; bone and joint radiology; head and neck-radiology; neuro-radiology. (H.W.). refs.; fig.; tabs

  2. Quality assessment for radiological model parameters

    International Nuclear Information System (INIS)

    Funtowicz, S.O.

    1989-01-01

    A prototype framework for representing uncertainties in radiological model parameters is introduced. This follows earlier development in this journal of a corresponding framework for representing uncertainties in radiological data. Refinements and extensions to the earlier framework are needed in order to take account of the additional contextual factors consequent on using data entries to quantify model parameters. The parameter coding can in turn feed in to methods for evaluating uncertainties in calculated model outputs. (author)

  3. Emergency radiological monitoring and analysis: Federal Radiological Monitoring and Assessment Center

    International Nuclear Information System (INIS)

    Thome, D.J.

    1995-01-01

    The US Federal Radiological Emergency Response Plan (FRERP) provides the framework for integrating the various Federal agencies responding to a major radiological emergency. The FRERP authorizes the creation of the Federal Radiological Monitoring and Assessment Center (FRMAC), which is established to coordinate all Federal agencies involved in the monitoring and assessment of the off-site radiological conditions in support of the impacted State(s) and the Lead Federal Agency (LFA). Within the FRMAC, the Monitoring and Analysis Division (M ampersand A) is responsible for coordinating all FRMAC assets involved in conducting a comprehensive program of environmental monitoring, sampling, radioanalysis, and quality assurance. To assure consistency, completeness, and the quality of the data produced, a methodology and procedures manual is being developed. This paper discusses the structure, assets, and operations of the FRMAC M ampersand A and the content and preparation of the manual

  4. Federal Radiological Monitoring and Assessment Center Phased Response Operations

    International Nuclear Information System (INIS)

    Riland, C.A.; Bowman, D.R.

    1999-01-01

    A Federal Radiological Monitoring and Assessment Center (FRMAC) is established in response to the Lead Federal Agency (LFA) or state request when a major radiological emergency is anticipated of has occurred. The FRMAC becomes a coalition of federal off-site monitoring and assessment activities to assist the LFA, state(s), local, and tribal authorities. State, local, and tribal authorities are invited to co-locate and prioritize monitoring and assessment efforts in the FRMAC. The Department of Energy is tasked by the Federal Radiological Emergency Response Plan to coordinate the FRMAC

  5. Effective dose delivered by conventional radiology to Aosta Valley population between 2002 and 2009

    Science.gov (United States)

    Zenone, F; Aimonetto, S; Catuzzo, P; Peruzzo Cornetto, A; Marchisio, P; Natrella, M; Rosanò, A M; Meloni, T; Pasquino, M; Tofani, S

    2012-01-01

    Objective Medical diagnostic procedures can be considered the main man-made source of ionising radiation exposure for the population. Conventional radiography still represents the largest contribution to examination frequency. The present work evaluates procedure frequency and effective dose from the majority of conventional radiology examinations performed at the Radiological Department of Aosta Hospital from 2002 to 2009. Method Effective dose to the patient was evaluated by means of the software PCXMC. Data provided by the radiological information system allowed us to obtain collective effective and per caput dose. Results The biggest contributors to per caput effective dose from conventional radiology are vertebral column, abdomen, chest, pelvis and (limited to females) breast. Vertebral column, pelvis and breast procedures show a significant dose increment in the period of the study. The mean effective dose per inhabitant from conventional radiology increased from 0.131 mSv in 2002 to 0.156 mSv in 2009. Combining these figures with those from our study of effective dose from CT (0.55 mSv in 2002 to 1.03 mSv in 2009), the total mean effective dose per inhabitant increased from 0.68 mSv to 1.19 mSv. The contribution of CT increased from 81% to 87% of the total. In contrast, conventional radiology accounts for 85% of the total number of procedures, but only 13% of the effective dose. Conclusion The study has demonstrated that conventional radiography still represents the biggest contributor to examination frequency in Aosta Valley in 2009. However, the frequency of the main procedures did not change significantly between 2002 and 2009. PMID:21937611

  6. Estimated collective effective dose to the population from radiological examinations in Slovenia

    Science.gov (United States)

    Zontar, Dejan; Zdesar, Urban; Kuhelj, Dimitrij; Pekarovic, Dean; Skrk, Damijan

    2015-01-01

    Background The aim of the study was to systematically evaluate population exposure from diagnostic and interventional radiological procedures in Slovenia. Methods The study was conducted in scope of the “Dose Datamed 2” project. A standard methodology based on 20 selected radiological procedures was adopted. Frequencies of the procedures were determined via questionnaires that were sent to all providers of radiological procedures while data about patient exposure per procedure were collected from existing databases. Collective effective dose to the population and effective dose per capita were estimated from the collected data (DLP for CT, MGD for mammography and DAP for other procedures) using dose conversion factors. Results The total collective effective dose to the population from radiological in 2011 was estimated to 1300 manSv and an effective dose per capita to 0.6 mSv of which approximately 2/3 are due to CT procedures. Conclusions The first systematic study of population exposure to ionising radiation from radiological procedures in Slovenia was performed. The results show that the exposure in Slovenia is under the European average. It confirmed large contributions of computed tomography and interventional procedures, identifying them as the areas that deserve special attention when it comes to justification and optimisation. PMID:25810709

  7. An assessment of the radiological impact of uranium mining in northern Saskatchewan

    International Nuclear Information System (INIS)

    1986-06-01

    This report presents the findings of a study which investigated the regional radiological impact of uranium mining in northern Saskatchewan. The study was performed by IEC Beak Consultants Ltd. under a contract awarded by Environment Canada in partnership with the Atomic Energy Control Board. This preliminary assessment suggests there is a negligible combined regional radiological impact from simultaneous operation of the three operating mines investigated as part of the present study. The mines are spaced too far apart for any superposition of emissions to be significantly greater than a small fraction of background levels. The most exposed individual not directly associated with any of the mining operations is estimated to receive a total radiation dose equal to about 3% of the dose due to natural background radiations. This increment is equivalent to the increment in natural background that would be received by an individual moving from Vancouver to Wollaston Post, before mining began in the area, as a result of reduced atmospheric shielding from cosmic radiation. Radiological impacts on biota are estimated to have insignficant effects on natural populations in all cases. However, since the study only investigates the effects of operational releases of radionuclides, the results do not imply that uranium mining developments will or will not have significant long-term radiological impact on northern Saskatchewan. Radiological impact assessments described in this report are estimates only. There are some uncertainties in the available data and modelling methodology. The radiological impact of abandoned tailings areas was not included in this study

  8. The system of radiation dose assessment and dose conversion coefficients in the ICRP and FGR

    Energy Technology Data Exchange (ETDEWEB)

    Kim, So Ra; Min, Byung Il; Park, Kihyun; Yang, Byung Mo; Suh, Kyung Suk [Nuclear Environmental Safety Research Division, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-12-15

    The International Commission on Radiological Protection (ICRP) recommendations and the Federal Guidance Report (FGR) published by the U.S. Environmental Protection Agency (EPA) have been widely applied worldwide in the fields of radiation protection and dose assessment. The dose conversion coefficients of the ICRP and FGR are widely used for assessing exposure doses. However, before the coefficients are used, the user must thoroughly understand the derivation process of the coefficients to ensure that they are used appropriately in the evaluation. The ICRP provides recommendations to regulatory and advisory agencies, mainly in the form of guidance on the fundamental principles on which appropriate radiological protection can be based. The FGR provides federal and state agencies with technical information to assist their implementation of radiation protection programs for the U.S. population. The system of radiation dose assessment and dose conversion coefficients in the ICRP and FGR is reviewed in this study. A thorough understanding of their background is essential for the proper use of dose conversion coefficients. The FGR dose assessment system was strongly influenced by the ICRP and the U.S. National Council on Radiation Protection and Measurements (NCRP), and is hence consistent with those recommendations. Moreover, the ICRP and FGR both used the scientific data reported by Biological Effects of Ionizing Radiation (BEIR) and United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) as their primary source of information. The difference between the ICRP and FGR lies in the fact that the ICRP utilized information regarding a population of diverse races, whereas the FGR utilized data on the American population, as its goal was to provide guidelines for radiological protection in the US. The contents of this study are expected to be utilized as basic research material in the areas of radiation protection and dose assessment.

  9. The system of radiation dose assessment and dose conversion coefficients in the ICRP and FGR

    International Nuclear Information System (INIS)

    Kim, So Ra; Min, Byung Il; Park, Kihyun; Yang, Byung Mo; Suh, Kyung Suk

    2016-01-01

    The International Commission on Radiological Protection (ICRP) recommendations and the Federal Guidance Report (FGR) published by the U.S. Environmental Protection Agency (EPA) have been widely applied worldwide in the fields of radiation protection and dose assessment. The dose conversion coefficients of the ICRP and FGR are widely used for assessing exposure doses. However, before the coefficients are used, the user must thoroughly understand the derivation process of the coefficients to ensure that they are used appropriately in the evaluation. The ICRP provides recommendations to regulatory and advisory agencies, mainly in the form of guidance on the fundamental principles on which appropriate radiological protection can be based. The FGR provides federal and state agencies with technical information to assist their implementation of radiation protection programs for the U.S. population. The system of radiation dose assessment and dose conversion coefficients in the ICRP and FGR is reviewed in this study. A thorough understanding of their background is essential for the proper use of dose conversion coefficients. The FGR dose assessment system was strongly influenced by the ICRP and the U.S. National Council on Radiation Protection and Measurements (NCRP), and is hence consistent with those recommendations. Moreover, the ICRP and FGR both used the scientific data reported by Biological Effects of Ionizing Radiation (BEIR) and United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) as their primary source of information. The difference between the ICRP and FGR lies in the fact that the ICRP utilized information regarding a population of diverse races, whereas the FGR utilized data on the American population, as its goal was to provide guidelines for radiological protection in the US. The contents of this study are expected to be utilized as basic research material in the areas of radiation protection and dose assessment

  10. Internal Dose Conversion Coefficients of Domestic Reference Animal and Plants for Dose Assessment of Non-human Species

    International Nuclear Information System (INIS)

    Keum, Dong Kwon; Jun, In; Lim, Kwang Muk; Choi, Yong Ho

    2009-01-01

    Traditionally, radiation protection has been focused on a radiation exposure of human beings. In the international radiation protection community, one of the recent key issues is to establish the methodology for assessing the radiological impact of an ionizing radiation on non-human species for an environmental protection. To assess the radiological impact to non-human species dose conversion coefficients are essential. This paper describes the methodology to calculate the internal dose conversion coefficient for non-human species and presents calculated internal dose conversion coefficients of 25 radionuclides for 8 domestic reference animal and plants

  11. The genetically significant dose from diagnostic radiology in Great Britain in 1977

    International Nuclear Information System (INIS)

    Darby, S.C.; Kendall, G.M.; Rae, S.; Wall, B.F.

    1980-09-01

    This report is the third in a series concerned with the annual genetically significant dose to the population of Great Britain from diagnostic radiology. It combines information from a frequency survey of diagnostic radiological examinations carried out in Great Britain in 1977 and estimates of gonadal doses for different examination types, together with population and child expectancy data. The annual genetically significant dose from diagnostic radiology carried out in Great Britain in 1977, is estimated to 118 μGy (11.8 millirad) of which 113 μGy (11.3 millirad) is contributed by diagnostic radiology carried out in National Health Service hospitals. There has been a sharp fall in the contribution from obstetric examinations since 1957 when the last national survey was carried out. The contribution from most other examination types is broadly similar and there is little evidence of a change in the overall level of genetically significant dose. This is in spite of an increase in the frequency of radiological examinations per thousand of the population of about 50 per cent. No significant differences were found as between England, Scotland and Wales. The British figure compares favourably with the levels of GSD reported from other countries with developed radiological services. (author)

  12. Capture and analysis of radiation dose reports for radiology

    International Nuclear Information System (INIS)

    Midgley, S.M.

    2014-01-01

    Radiographic imaging systems can produce records of exposure and dose parameters for each patient. A variety of file formats are in use including plain text, bit map images showing pictures of written text and radiation dose structured reports as text or extended markup language files. Whilst some of this information is available with image data on the hospital picture archive and communication system, access is restricted to individual patient records, thereby making it difficult to locate multiple records for the same scan protocol. This study considers the exposure records and dose reports from four modalities. Exposure records for mammography and general radiography are utilized for repeat analysis. Dose reports for fluoroscopy and computed tomography (CT) are utilized to study the distribution of patient doses for each protocol. Results for dosimetric quantities measured by General Radiography, Fluoroscopy and CT equipment are summarised and presented in the Appendix. Projection imaging uses the dose (in air) area product and derived quantities including the dose to the reference point as a measure of the air kerma reaching the skin, ignoring movement of the beam for fluoroscopy. CT uses the dose indices CTDIvol and dose length product as a measure of the dose per axial slice, and to the scanned volume. Suitable conversion factors are identified and used to estimate the effective dose to an average size patient (for CT and fluoroscopy) and the entrance skin dose for fluoroscopy.

  13. Population dose assessment: characteristics of PC CREAM

    International Nuclear Information System (INIS)

    Alonso, Maria T.; Curti, Adriana R.

    2000-01-01

    This paper presents the main features of the PC CREAM, a program for performing radiological impact assessments due to radioactive discharges into the environment during the operation of radioactive and nuclear facilities. PC CREAM is a suite of six programs that can be used to estimate individual and collective radiation doses. The methodology of PC CREAM is based on updated environmental and dosimetric models, including ICRP 60 recommendations. The models include several exposure pathways and the input files are easy to access. The ergonomics of the program improves the user interaction and makes easier the input of local data. This program is useful for performing sensitivity analysis, siting studies and validation of model comparing the activity concentration output data with environmental monitoring data. The methodology of each module is described as well as the output data. (author)

  14. Establishment of exposure dose assessment laboratory in National Radiation Emergency Medical Center (NREMC)

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, Jae Ryong; Ha, Wi Ho; Yoon, Seok Won; Han, Eun Ae; Lee, Seung Sook [Korea Institute of Radiological and Medical Sciences, Seoul (Korea, Republic of)

    2011-10-15

    As unclear industry grown, 432 of the nuclear power plants are operating and 52 of NPPs are under construction currently. Increasing use of radiation or radioisotopes in the field of industry, medical purpose and research such as non-destructive examination, computed tomography and x-ray, etc. constantly. With use of nuclear or radiation has incidence possibility for example the Fukushima NPP incident, the Goiania accident and the Chernobyl Nuclear accident. Also the risk of terror by radioactive material such as Radiological Dispersal Device(RDD) etc. In Korea, since the 'Law on protection of nuclear facilities and countermeasure for radioactive preparedness was enacted in 2003, the Korean institute of Radiological and Medical Sciences(KIRAMS) was established for the radiation emergency medical response in radiological disaster due to nuclear accident, radioactive terror and so on. Especially National Radiation Emergency Medical Center(NREMC) has the duty that is protect citizens from nuclear, radiological accidents or radiological terrors through the emergency medical preparedness. The NREMC was established by the 39-article law on physical protection of nuclear material and facilities and measures for radiological emergencies. Dose assessment or contamination survey should be performed which provide the radiological information for medical response. For this reason, the NREMC establish and re-organized dose assessment system based on the existing dose assessment system of the NREMC recently. The exposure dose could be measured by physical and biological method. With these two methods, we can have conservative dose assessment result. Therefore the NREMC established the exposure dose assessment laboratory which was re-organized laboratory space and introduced specialized equipment for dose assessment. This paper will report the establishment and operation of exposure dose assessment laboratory for radiological emergency response and discuss how to enhance

  15. assessment of radiological hazard indices from surface soil to ...

    African Journals Online (AJOL)

    samples in Eagle, Atlas and rock cement companies in Port Harcourt was carried out by ... and external hazard indices in order to assess the radiological implication to the people .... Sciences & Environmental Management, Vol. 9, No. 3, pp.

  16. Methodology for Radiological Risk Assessment of Deep Borehole Disposal Operations

    Energy Technology Data Exchange (ETDEWEB)

    Hardin, Ernest; Su, Jiann-Cherng; Peretz, Fred(ORNL)

    2017-03-01

    The primary purpose of the preclosure radiological safety assessment (that this document supports) is to identify risk factors for disposal operations, to aid in design for the deep borehole field test (DBFT) engineering demonstration.

  17. Committed dose equivalent in the practice of radiological protection

    International Nuclear Information System (INIS)

    Nenot, J.C.; Piechowski, J.

    1985-01-01

    In the case of internal exposure, the dose is not received at the moment of exposure, as happens with external exposure, since the incorporated radionuclide irradiates the various organs and tissues during the time it is present in the body. By definition, the committed dose equivalent corresponds to the received dose integrated over 50 years from the date of intake. In order to calculate it, one has to know the intake activity and the value of the committed dose equivalent per unit of intake activity. The uncertainties of the first parameter are such that the committed dose equivalent can only be regarded as an order of magnitude and not as a very accurate quantity. The use of it is justified, however, for, like the dose equivalent for external exposure, it expresses the risk of stochastic effects for the individual concerned since these effects, should they appear, would do so only after a latent period which is generally longer than the dose integration time. Moreover, the use of the committed dose equivalent offers certain advantages for dosimetric management, especially when it is simplified. A practical problem which may arise is that the annual dose limit is apparently exceeded by virtue of the fact that one is taking account, in the first year, of doses which will actually be received only in the following years. These problems are rare enough in practice to be dealt with individually in each case. (author)

  18. Emergency radiological monitoring and analysis United States Federal Radiological Monitoring and Assessment Center

    International Nuclear Information System (INIS)

    Thome, D.J.

    1994-01-01

    The United States Federal Radiological Emergency Response Plan (FRERP) provides the framework for integrating the various Federal agencies responding to a major radiological emergency. Following a major radiological incident the FRERP authorizes the creation of the Federal Radiological Monitoring and Assessment Center (FRMAC). The FRMAC is established to coordinate all Federal agencies involved in the monitoring and assessment of the off-site radiological conditions in support of the impacted states and the Lead Federal Agency (LFA). Within the FRMAC, the Monitoring and Analysis Division is responsible for coordinating all FRMAC assets involved in conducting a comprehensive program of environmental monitoring, sampling, radioanalysis and quality assurance. This program includes: (1) Aerial Radiological Monitoring - Fixed Wing and Helicopter, (2) Field Monitoring and Sampling, (3) Radioanalysis - Mobile and Fixed Laboratories, (4) Radiation Detection Instrumentation - Calibration and Maintenance, (5) Environmental Dosimetry, and (6) An integrated program of Quality Assurance. To assure consistency, completeness and the quality of the data produced, a methodology and procedures handbook is being developed. This paper discusses the structure, assets and operations of FRMAC monitoring and analysis and the content and preparation of this handbook

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2003-06-01

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

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

    International Nuclear Information System (INIS)

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

    2003-01-01

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

  1. Absorbed dose to the skin in radiological examinations of upper and lower gastrointestinal tract

    International Nuclear Information System (INIS)

    Zonca, G.; Brusa, A.; Somigliana, A.; Pasqualotto, C.; Sichirollo, A.E.; Bellomi, M.; Cozzi, G.; Severini, A.

    1995-01-01

    Absorbed doses to the skin in radiological examinations of the upper and lower gastronintestinal tract in conventional and digital radiology are evaluated and compared. Absorbed doses were measured with LiF thermoluminescence dosemeters placed on the lower pelvis, umbilicus and forehead of the patient to evaluate the absorbed dose in and outside the primary beam. On 10 patients a reduction in absorbed dose of about 34% for double contrast barium enema and of 66% for upper gastrointestinal tract examinations was revealed with digital radiography equipment. In our working conditions the lower dose requirement for digital radiography is mainly due to image intensifiers and television chains and also, due to our equipment settings, to the dose reduction with digital spot fluorography compared with conventional spot film radiography. (Author)

  2. Dose assessment activities in the Republic of the Marshall Islands

    International Nuclear Information System (INIS)

    Simon, S.L.; Graham, J.C.

    1996-01-01

    Dose assessments, both retrospective and prospective, comprise one important function of a radiological study commissioned by the Republic of the Marshall Islands (RMI) government in late 1989. Estimating past or future exposure requires the synthesis of information from historical data, results from a recently completed field monitoring program, laboratory measurements, and some experimental studies. Most of the activities in the RMI to date have emphasized a pragmatic rather than theoretical approach. In particular, most of the recent effort has been expended on conducting an independent radiological monitoring program to determine the degree of deposition and the geographical extent of weapons test fallout over the nation. Contamination levels on 70% of the land mass of the Marshall Islands were unknown prior to 1994. The environmental radioactivity data play an integral role in both retrospective and prospective assessments. One recent use of dose assessment has been to interpret environmental measurements of radioactivity into annual doses that might be expected at every atoll. A second use for dose assessment has been to determine compliance with dose action level for the rehabitation of Rongelap Island. Careful examination of exposure pathways relevant to the island lifestyle has been necessary to accommodate these purposes. Finally, an examination is underway of gummed film, fixed-instrument, and aerial survey data accumulated during the 1950's by the Health and Safety Laboratory of the U.S. AEC. This article gives an overview of these many different activities and a summary of recent dose assessments

  3. CUEX methodology for assessing radiological impacts in the context of ICRP Recommendations

    International Nuclear Information System (INIS)

    Rohwer, P.S.; Kaye, S.V.; Struxness, E.G.

    1975-01-01

    The Cumulative Exposure Index (CUEX) methodology was developed to estimate and assess, in the context of International Commission on Radiological Protection (ICRP) Recommendations, the total radiation dose to man due to environmental releases of radioactivity from nuclear applications. Each CUEX, a time-integrated radionuclide concentration (e.g.μCi.h.cm -3 ), reflects the selected annual dose limit for the reference organ and the estimated total dose to that organ via all exposure modes for a specific exposure situation. To assess the radiological significance of an environmental release of radioactivity, calculated or measured radionuclide concentrations in a suitable environmental sampling medium are compared with CUEXs determined for that medium under comparable conditions. The models and computer codes used in the CUEX methodology to predict environmental transport and to estimate radiation dose have been thoroughly tested. These models and codes are identified and described briefly. Calculation of a CUEX is shown step by step. An application of the methodology to a hypothetical atmospheric release involving four radionuclides illustrates use of the CUEX computer code to assess the radiological significance of a release, and to determine the relative importance (i.e. percentage of the estimated total dose contributed) of each radionuclide and each mode of exposure. The data requirements of the system are shown to be extensive, but not excessive in view of the assessments and analyses provided by the CUEX code. (author)

  4. Offsite dose calculation manual guidance: Standard radiological effluent controls for boiling water reactors

    International Nuclear Information System (INIS)

    Meinke, W.W.; Essig, T.H.

    1991-04-01

    This report contains guidance which may be voluntarily used by licensees who choose to implement the provision of Generic Letter 89-- 01, which allows Radiological Effluent Technical Specifications (RETS) to be removed from the main body of the Technical Specifications and placed in the Offsite Dose Calculation Manual (ODCM). Guidance is provided for Standard Effluent Controls definitions, Controls for effluent monitoring instrumentation, Controls for effluent releases, Controls for radiological environmental monitoring, and the basis for Controls. Guidance on the formulation of RETS has been available in draft form for a number of years; the current effort simply recasts those RETS into Standard Radiological Effluent Controls for application to the ODCM. 11 tabs

  5. Radiation doses in pediatric radiology: influence of regulations and standards

    International Nuclear Information System (INIS)

    Suleiman, O.H.

    2004-01-01

    The benefits of X-ray examinations contribute to the quality of modern medicine; however the risk of using X-rays, a carcinogen, has always been a concern. This concern is heightened for pediatric patients, who have a much greater sensitivity to the carcinogenic effects of radiation than adults. The principle of as low as reasonably achievable, or ALARA, is essential for minimizing the radiation dose patients receive, especially for pediatric patients. In order to keep radiation doses ALARA, one must know the dose patients receive. The determination of radiation dose in a standard way is therefore necessary so that these doses can be compared with practice, and for meaningful comparison against voluntary standards. In extreme situations, where public health needs may require mandatory standards, or regulations, the quantitative measurement and calculation of radiation dose becomes essential. How some radiation dose metrics and standards have evolved, including the value of different metrics such as entrance air kerma, organ dose, and effective dose will be presented. Recent pediatric X-ray studies, whether or not dedicated pediatric equipment is necessary, and recent initiatives by the Food and Drug Administration for pediatric population will be discussed. (orig.)

  6. Discharges of nuclear waste into the Kola Bay and its impact on human radiological doses

    International Nuclear Information System (INIS)

    Matishov, Genady G.; Matishov, Dimitry G.; Namjatov, Alexey A.; Carroll, JoLynn; Dahle, Salve

    2000-01-01

    The civilian nuclear icebreaker facility, RTP ''ATOMFLOT,'' is located in Kola Bay, Northwest Russia, as are several nuclear installations operated by the Russian Northern Fleet. A treatment plant at the Atomflot facility discharges purified nuclear waste into the bay at an annual rate of 500 m 3 . As a result of plant modifications this rate will soon increase to 5000 m 3 /yr. Evidence of minor leakages of 60 Co are reported by in the vicinity of Atomflot as well as near several military installations in Kola and the adjacent Motovsky Bays. 137 Cs levels reported in the present study for seawater and seaweed collected from locations within the bays are at expected levels except in the vicinity of Atomflot, where the 137 Cs level in a seaweed sample was 46±5 Bq/kg w.w. indicating significant uptake of radionuclides to biota. Uptake also may be occurring in higher trophic levels of the food web through environmental exchange and/or biotransformation. We consider the impact of the present and anticipated discharges from Atomflot through a radiological dose assessment for humans consuming fish from Kola Bay. Mixing and transport of nuclear waste is simulated using a simple box model. Maximum doses, assuming consumption of 100 kg/yr of fish, are below 10 -9 Sv/yr; the planned ten-fold increase in the discharge of treated waste will increase the doses to below 10 -8 Sv/yr. Using data on radionuclide levels in sediments and assuming equilibrium partitioning of radionuclides among sediment, seawater and fish, we estimate that the total doses to humans consuming fish from different areas of Kola and Motovsky Bays, including adjacent to military-controlled nuclear installations, are ∼10 -7 Sv/yr. Nuclear activities in Kola and Motovsky Bays thus far have had minimal impact on the environment. Discharges from the treatment plant currently account for less than 0.2% of the total dose predictions. The increase in discharges from the treatment plant is not expected to change

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

    International Nuclear Information System (INIS)

    WEISS, E.V.

    2000-01-01

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

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

    CERN Document Server

    Weiss, E V

    2000-01-01

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

  9. Radiological Risk Assessment of Capstone Depleted Uranium Aerosols

    International Nuclear Information System (INIS)

    Hahn, Fletcher; Roszell, Laurie E.; Daxon, Eric G.; Guilmette, Ray A.; Parkhurst, MaryAnn

    2009-01-01

    Assessment of the health risk from exposure to aerosols of depleted uranium (DU) is an important outcome of the Capstone aerosol studies that established exposure ranges to personnel in armored combat vehicles perforated by DU munitions. Although the radiation exposure from DU is low, there is concern that DU deposited in the body may increase cancer rates. Radiation doses to various organs of the body resulting from the inhalation of DU aerosols measured in the Capstone studies were calculated using International Commission on Radiological Protection (ICRP) models. Organs and tissues with the highest calculated committed equivalent 50-yr doses were lung and extrathoracic tissues (nose and nasal passages, pharynx, larynx, mouth and thoracic lymph nodes). Doses to the bone surface and kidney were about 5 to 10% of the doses to the extrathoracic tissues. The methodologies of the ICRP International Steering Committee on Radiation Standards (ISCORS) were used for determining the whole body cancer risk. Organ-specific risks were estimated using ICRP and U.S. Environmental Protection Agency (EPA) methodologies. Risks for crew members and first responders were determined for selected scenarios based on the time interval of exposure and for vehicle and armor type. The lung was the organ with the highest cancer mortality risk, accounting for about 97% of the risks summed from all organs. The highest mean lifetime risk for lung cancer for the scenario with the longest exposure time interval (2 h) was 0.42%. This risk is low compared with the natural or background risk of 7.35%. These risks can be significantly reduced by using an existing ventilation system (if operable) and by reducing personnel time in the vehicle immediately after perforation

  10. Radiological risk assessment of Capstone depleted uranium aerosols.

    Science.gov (United States)

    Hahn, Fletcher F; Roszell, Laurie E; Daxon, Eric G; Guilmette, Raymond A; Parkhurst, Mary Ann

    2009-03-01

    Assessment of the health risk from exposure to aerosols of depleted uranium (DU) is an important outcome of the Capstone aerosol studies that established exposure ranges to personnel in armored combat vehicles perforated by DU munitions. Although the radiation exposure from DU is low, there is concern that DU deposited in the body may increase cancer rates. Radiation doses to various organs of the body resulting from the inhalation of DU aerosols measured in the Capstone studies were calculated using International Commission on Radiological Protection (ICRP) models. Organs and tissues with the highest calculated committed equivalent 50-y doses were lung and extrathoracic tissues (nose and nasal passages, pharynx, larynx, mouth, and thoracic lymph nodes). Doses to the bone surface and kidney were about 5 to 10% of the doses to the extrathoracic tissues. Organ-specific risks were estimated using ICRP and U.S. Environmental Protection Agency (EPA) methodologies. Risks for crewmembers and first responders were determined for selected scenarios based on the time interval of exposure and for vehicle and armor type. The lung was the organ with the highest cancer mortality risk, accounting for about 97% of the risks summed from all organs. The highest mean lifetime risk for lung cancer for the scenario with the longest exposure time interval (2 h) was 0.42%. This risk is low compared with the natural or background risk of 7.35%. These risks can be significantly reduced by using an existing ventilation system (if operable) and by reducing personnel time in the vehicle immediately after perforation.

  11. Paediatric radiology and scientific contributions to radiation dose at the meeting of the German Radiological Society-An analysis of an 11-year period

    International Nuclear Information System (INIS)

    Heyer, Christoph M.; Lemburg, Stefan P.; Peters, Soeren A.

    2010-01-01

    Aim: Evaluation of the emphasis on themes pertaining to paediatric radiology and radiation dose at the Meeting of the German Radiological Society from 1998 to 2008 in comparison to international data. Materials and methods: Retrospective analysis of 9440 abstracts with documentation of type of contribution, imaging modality, and examined body region. Abstracts primarily dealing with paediatric radiology and those stating radiation dose were documented. Results were compared with a Pubmed query. Results: 448 contributions in paediatric radiology were presented corresponding to 5% of all abstracts with an increase from 5 (1998) to 7% (2008). The proportion of prospective studies of all congress contributions was 10%, whereas in paediatric radiology, the share of prospective studies was 6%. From 1998 to 2008, the share of MRI fell from 48 to 38%, while CT contributions rose from 30 to 34%. Within paediatric radiology, the proportion of CT rose from 23 to 29%, while MRI and ultrasound fell from 63 to 48% and 35 to 19%, respectively. The share of abstracts dealing with radiation dose rose from 7 to 10% while that primarily pertaining to dose reduction grew from 2 to 4%. Of all abstracts concerning CT, 15% touched on radiation dose, whereas 6% primarily dealt with dose reduction. Among all abstracts dealing with paediatric radiology, 20 and 6% mentioned radiation dose and dose reduction, respectively. In the subgroup of paediatric radiology CT abstracts, radiation dose and dose reduction were mentioned in 34 and 16%, respectively. An online query produced 137,791 publications on CT, of whose abstracts 3% mentioned radiation dose and 0.5% mentioned dose reduction. 11% of all CT publications dealt with paediatric populations and 2% of these publications examined questions of radiation dose. Conclusions: In the last 11 years the Meeting of the German Radiological Society has presented a growing number of contributions pertaining to paediatric radiology. CT has shown the

  12. Federal Radiological Monitoring and Assessment Center: Phase I Response

    International Nuclear Information System (INIS)

    Riland, C.; Bowman, D.R.; Lambert, R.; Tighe, R.

    1999-01-01

    A Federal Radiological Monitoring and Assessment Center (FRMAC) is established in response to a Lead Federal Agency (LFA) or State request when a radiological emergency is anticipated or has occurred. The FRMAC coordinates the off-site monitoring, assessment, and analysis activities during such an emergency. The FRMAC response is divided into three phases. FRMAC Phase 1 is a rapid, initial-response capability that can interface with Federal or State officials and is designed for a quick response time and rapid radiological data collection and assessment. FRMAC Phase 1 products provide an initial characterization of the radiological situation and information on early health effects to officials responsible for making and implementing protective action decisions

  13. BNL ALARA center's development of a computerized Radiological Assessment and Design System (RADS)

    International Nuclear Information System (INIS)

    Dionne, B.J.; Connelly, J.M.

    1993-01-01

    The US Department of Energy's (DOE) Office of Health Physics and Industrial Hygiene sponsored a study of Radiological Engineering Programs at selected DOE contractor facilities. This study was conducted to review, evaluate, and summarize techniques and practices that should be considered in the design phase that reduce dose and the spread of radioactive materials during subsequent construction and operation at DOE radiological facilities. As in a previous study on operational ALARA programs, a variety of open-quotes good-practice documentsclose quotes will be generated. It is envisioned that these documents will serve as a resource to assist radiological engineers in the process of designing radiological facilities, and in performing radiological safety/ALARA design reviews. This paper presents the features for three good-practice documents and related software applications that are being developed based on the findings of this study. The proposed software called open-quotes Radiological Assessment and Design Systemclose quotes (RADS) will be a menu-driven database and spreadsheet program. It will be designed to provide easy, consistent, and effective implementation of the methodologies described in the three good-practice documents. These documents and the associated RADS software will provide the user with the following three functions: (1) enter dose assessment information and data into computer worksheets and provide printed tables of the results which can then be inserted into safety analysis reports or cost-benefit analysis, (2) perform a wide variety of sorts of radiological design criteria from DOE Orders and produce a checklist of the desired design criteria, and (3) enter cost/benefit data and qualitative ratings of attributes for various design alternatives which reduce dose into computer worksheets and provide printed reports of cost-effectiveness results

  14. BNL ALARA Center's development of a computerized radiological assessment and design system (RADS)

    International Nuclear Information System (INIS)

    Dionne, B.J.; Masciulli, S.; Connelly, J.M.

    1993-01-01

    The US Department of Energy's (DOE) Office of Health Physics and Industrial Hygiene sponsored a study of Radiological Engineering Programs at selected DOE contractor facilities. This study was conducted to review, evaluate, and summarize techniques and practices that should be considered in the design phase that reduce dose and the spread of radioactive materials during subsequent construction and operation of DOE radiological facilities. As in a previous study on operational ALARA programs, a variety of good-practice documents will be generated. It is envisioned that these documents will serve as a resource to assist radiological engineers in the process of designing radiological facilities, and in performing radiological safety/ALARA design reviews. This paper presents the features for three good-practice documents and related software applications that are being developed based on the findings of this study. The proposed software called Radiological Assessment and Design System (RADS) will be a menu-driven database and spreadsheet program. It will be designed to provide easy, consistent, and effective implementation of the methodologies described in the three good-practice documents. These documents and the associated RADS software will provide the user with the following three functions: (1) enter dose assessment information and data into computer worksheets and provide printed tables of the results which can then be inserted into safety analysis reports or cost-benefit analyses, (2) perform a wide variety of sorts of radiological design criteria from DOE Orders and produce a checklist of the desired design criteria, and (3) enter cost/benefit data and qualitative rating of attributes for various design alternatives which reduce dose into computer worksheets and provide printed reports of cost-effectiveness results

  15. Assessment of the radiological impact of contaminated discharges

    Energy Technology Data Exchange (ETDEWEB)

    Sweeck, L; Zeevaert, T

    1996-09-18

    A biosphere model has been used to calculate the release of radionuclides from contaminated soils and their dose impact on critical individuals in the environment. Normal evolution and accidental scenarios are considered. The objective of the model is to provide an indication of the radiological risk rather than to predict its future impact.

  16. Doses to patients from diagnostic radiology in Romania

    International Nuclear Information System (INIS)

    Iacob, O.; Diaconescu, C.

    2001-01-01

    Effective doses to over 2400 patients undergoing 20 of the most important types of X-ray examinations have been estimated from entrance surface doses or dose-area products, measured in 27 X-ray departments, and the appropriate conversion coefficients calculated by the NRPB for six mathematical phantoms representing 0, 1, 5, 10, 15 year old children and the adult. The patient-weighted mean effective dose from X-ray examinations performed annually in Romania is 1.32 mSv, with 1.40 mSv for the average adult patient and 0,59 mSv for the average paediatric patient. The corresponding annual collective effective dose is about 13,430 man Sv, with the main contribution belonging to adult patients (95%), the remainder of 5 percent - to paediatric patients. (author)

  17. Radiological dose and metadata management; Radiologisches Dosis- und Metadatenmanagement

    Energy Technology Data Exchange (ETDEWEB)

    Walz, M.; Madsack, B. [TUeV SUeD Life Service GmbH, Aerztliche Stelle fuer Qualitaetssicherung in der Radiologie, Nuklearmedizin und Strahlentherapie Hessen, Frankfurt (Germany); Kolodziej, M. [INFINITT Europe GmbH, Frankfurt/M (Germany)

    2016-12-15

    This article describes the features of management systems currently available in Germany for extraction, registration and evaluation of metadata from radiological examinations, particularly in the digital imaging and communications in medicine (DICOM) environment. In addition, the probable relevant developments in this area concerning radiation protection legislation, terminology, standardization and information technology are presented. (orig.) [German] Dieser Artikel stellt die aktuell in Deutschland verfuegbaren Funktionen von Managementsystemen zur Erfassung und Auswertung von Metadaten zu radiologischen Untersuchungen insbesondere im DICOM-Umfeld (Digital Imaging and Communications in Medicine) vor. Ausserdem werden die in diesem Bereich voraussichtlich relevanten Entwicklungen von Strahlenschutzgesetzgebung ueber Terminologie und Standardisierung bis zu informationstechnischen Aspekten dargestellt. (orig.)

  18. Radiological Information Management System - an effective tool for radiological information dissemination and dose control

    International Nuclear Information System (INIS)

    Sharma, Ravikant; Singh, Mintoo; Abhishek, Neel; Yadav, Umed

    2012-01-01

    Information is a key element for success of an organization, and timely information is a guarantee to success. To meet this essential requirement, Health Physics Unit at RAPS-5 and 6 has conceived, designed and implemented a comprehensive integrated network based system, named Radiological Information Management System (RIMS). The complete system is designed on the principle of FOUR ONE's i.e. ONE data entry by ONE individual at ONE time using ONE system/client

  19. Design and implementation of wireless dose logger network for radiological emergency decision support system

    International Nuclear Information System (INIS)

    Gopalakrishnan, V.; Baskaran, R.; Venkatraman, B.

    2016-01-01

    A decision support system (DSS) is implemented in Radiological Safety Division, Indira Gandhi Centre for Atomic Research for providing guidance for emergency decision making in case of an inadvertent nuclear accident. Real time gamma dose rate measurement around the stack is used for estimating the radioactive release rate (source term) by using inverse calculation. Wireless gamma dose logging network is designed, implemented, and installed around the Madras Atomic Power Station reactor stack to continuously acquire the environmental gamma dose rate and the details are presented in the paper. The network uses XBee–Pro wireless modules and PSoC controller for wireless interfacing, and the data are logged at the base station. A LabView based program is developed to receive the data, display it on the Google Map, plot the data over the time scale, and register the data in a file to share with DSS software. The DSS at the base station evaluates the real time source term to assess radiation impact.

  20. Design and implementation of wireless dose logger network for radiological emergency decision support system.

    Science.gov (United States)

    Gopalakrishnan, V; Baskaran, R; Venkatraman, B

    2016-08-01

    A decision support system (DSS) is implemented in Radiological Safety Division, Indira Gandhi Centre for Atomic Research for providing guidance for emergency decision making in case of an inadvertent nuclear accident. Real time gamma dose rate measurement around the stack is used for estimating the radioactive release rate (source term) by using inverse calculation. Wireless gamma dose logging network is designed, implemented, and installed around the Madras Atomic Power Station reactor stack to continuously acquire the environmental gamma dose rate and the details are presented in the paper. The network uses XBee-Pro wireless modules and PSoC controller for wireless interfacing, and the data are logged at the base station. A LabView based program is developed to receive the data, display it on the Google Map, plot the data over the time scale, and register the data in a file to share with DSS software. The DSS at the base station evaluates the real time source term to assess radiation impact.

  1. Design and implementation of wireless dose logger network for radiological emergency decision support system

    Energy Technology Data Exchange (ETDEWEB)

    Gopalakrishnan, V.; Baskaran, R.; Venkatraman, B. [Radiation Impact Assessment Section, Radiological Safety Division, Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam 603102 (India)

    2016-08-15

    A decision support system (DSS) is implemented in Radiological Safety Division, Indira Gandhi Centre for Atomic Research for providing guidance for emergency decision making in case of an inadvertent nuclear accident. Real time gamma dose rate measurement around the stack is used for estimating the radioactive release rate (source term) by using inverse calculation. Wireless gamma dose logging network is designed, implemented, and installed around the Madras Atomic Power Station reactor stack to continuously acquire the environmental gamma dose rate and the details are presented in the paper. The network uses XBee–Pro wireless modules and PSoC controller for wireless interfacing, and the data are logged at the base station. A LabView based program is developed to receive the data, display it on the Google Map, plot the data over the time scale, and register the data in a file to share with DSS software. The DSS at the base station evaluates the real time source term to assess radiation impact.

  2. Dose assessments for SFR 1

    International Nuclear Information System (INIS)

    Bergstroem, Ulla; Avila, Rodolfo; Ekstroem, Per-Anders; Cruz, Idalmis de la

    2008-05-01

    Following a review by the Swedish regulatory authorities of the safety analysis of the SFR 1 disposal facility for low and intermediate level waste, SKB has prepared an updated safety analysis, SAR-08. This report presents estimations of annual doses to the most exposed groups from potential radionuclide releases from the SFR 1 repository for a number of calculation cases, selected using a systematic approach for identifying relevant scenarios for the safety analysis. The dose estimates can be used for demonstrating that the long term safety of the repository is in compliance with the regulatory requirements. In particular, the mean values of the annual doses can be used to estimate the expected risks to the most exposed individuals, which can then be compared with the regulatory risk criteria for human health. The conversion from doses to risks is performed in the main report. For one scenario however, where the effects of an earthquake taking place close to the repository are analysed, risk calculations are presented in this report. In addition, prediction of concentrations of radionuclides in environmental media, such as water and soil, are compared with concentration limits suggested by the Erica-project as a base for estimating potential effects on the environment. The assessment of the impact on non-human biota showed that the potential impact is negligible. Committed collective dose for an integration period of 10,000 years for releases occurring during the first thousand years after closure are also calculated. The collective dose commitment was estimated to be 8 manSv. The dose calculations were carried out for a period of 100,000 years, which was sufficient to observe peak doses in all scenarios considered. Releases to the landscape and to a well were considered. The peaks of the mean annual doses from releases to the landscape are associated with C-14 releases to a future lake around year 5,000 AD. In the case of releases to a well, the peak annual doses

  3. Dose assessments for SFR 1

    Energy Technology Data Exchange (ETDEWEB)

    Bergstroem, Ulla (Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden)); Avila, Rodolfo; Ekstroem, Per-Anders; Cruz, Idalmis de la (Facilia AB, Bromma (Sweden))

    2008-06-15

    Following a review by the Swedish regulatory authorities of the safety analysis of the SFR 1 disposal facility for low and intermediate level waste, SKB has prepared an updated safety analysis, SAR-08. This report presents estimations of annual doses to the most exposed groups from potential radionuclide releases from the SFR 1 repository for a number of calculation cases, selected using a systematic approach for identifying relevant scenarios for the safety analysis. The dose estimates can be used for demonstrating that the long term safety of the repository is in compliance with the regulatory requirements. In particular, the mean values of the annual doses can be used to estimate the expected risks to the most exposed individuals, which can then be compared with the regulatory risk criteria for human health. The conversion from doses to risks is performed in the main report. For one scenario however, where the effects of an earthquake taking place close to the repository are analysed, risk calculations are presented in this report. In addition, prediction of concentrations of radionuclides in environmental media, such as water and soil, are compared with concentration limits suggested by the Erica-project as a base for estimating potential effects on the environment. The assessment of the impact on non-human biota showed that the potential impact is negligible. Committed collective dose for an integration period of 10,000 years for releases occurring during the first thousand years after closure are also calculated. The collective dose commitment was estimated to be 8 manSv. The dose calculations were carried out for a period of 100,000 years, which was sufficient to observe peak doses in all scenarios considered. Releases to the landscape and to a well were considered. The peaks of the mean annual doses from releases to the landscape are associated with C-14 releases to a future lake around year 5,000 AD. In the case of releases to a well, the peak annual doses

  4. Correlation between effective dose and radiological risk: general concepts

    Energy Technology Data Exchange (ETDEWEB)

    Costa, Paulo Roberto; Yoshimura, Elisabeth Mateus; Nersissian, Denise Yanikian; Melo, Camila Souza, E-mail: pcosta@if.usp.br [Universidade de Sao Paulo (IF/USP), Sao Paulo, SP (Brazil). Instituto de Fisica

    2016-05-15

    The present review aims to offer an educational approach related to the limitations in the use of the effective dose magnitude as a tool for the quantification of doses resulting from diagnostic applications of ionizing radiation. We present a critical analysis of the quantities accepted and currently used for dosimetric evaluation in diagnostic imaging procedures, based on studies published in the literature. It is highlighted the use of these quantities to evaluate the risk attributed to the procedure and to calculate the effective dose, as well as to determine its correct use and interpretation. (author)

  5. Radiology

    International Nuclear Information System (INIS)

    Edholm, P.R.

    1990-01-01

    This is a report describing diagnostic techniques used in radiology. It describes the equipment necessary for, and the operation of a radiological department. Also is described the standard methods used in radiodiagnosis. (K.A.E.)

  6. Radiological procedures: Quality criteria and dose optimisation: French status

    International Nuclear Information System (INIS)

    Grenier, Ph.; Marshall-Depommier, E.; Bourguignon, M.; Beauvais-March, H.; Valero, M.; Lacronique, J.F.; Frijal, G.

    2001-01-01

    The Council Directive 97/43/Euratom of June 30 1997 on health protection of individuals against the dangers of ionising radiation in relation to medical exposure has come into force on May, 13 th 2000. French health directorate has entrusted the 'Office de Protection contre les Rayonnements Ionisants (OPRI)' together with the 'Societe Francaise de Radiologie' (SFR) to implement article 6 related to radiological procedures, in order to bring into operation the principle of optimisation. The most frequent diagnostic radiology and interventional procedures (120 protocols) have been standardised in writing. Corresponding patient dosimetry has been determined from measurements on site, calculations and literature review. The criteria for optimisation have been highlighted for each protocols. With the help of the French Society of Medical Physicists (SFPM), measurements are being collected on a large scale in France. Then, knowing more precisely the patient dosimetry of each protocol, referral criteria will be reviewed and prioritised to implement the principle of justification. The authors will present and explain the chosen methodology (methodology of the Accreditation and Evaluation in Health Agency: ANAES) for completing this two years workload program, and will demonstrate clinical examples as well. (author)

  7. Comparative study about doses and radiological protection in gastrointestinal fluoroscopy

    International Nuclear Information System (INIS)

    Caneravo, L.V.; Borges, J.C.; Carlos, M.T.; Koch, H.A.

    1996-01-01

    The Radiation Protection and Dosimetry Institute of the National Nuclear Energy Commission (IRD/CNEN) and the Radiodiagnostic Service of the Rio de Janeiro Federal University Hospital, have been engaged in the development of quality control programs applied to radiodiagnostics, one of them concerning gastrointestinal fluoroscopy. Since fluoroscopy examinations normally deal with high doses, they represent an important fraction of public exposure. They deserve special attention and the risks to patients should be considered individually, not only as a population statistics. Another target should be the search for procedures that reduce doses to patients and, therefore, reduce dose to medical staff involved. This work describes steps followed and results obtained in the estimation of doses for patients and physicians. Investigated examinations were esophagography, gastroduodenal seriographic and colon with double contrast media, using conventional equipment with fluorescent screens, carried on by physicians engaged in the first year of medical residence. (authors). 9 refs., 1 fig., 2 tabs

  8. Generic procedures for assessment and response during a radiological emergency

    International Nuclear Information System (INIS)

    2000-08-01

    One of the most important aspects of managing a radiological emergency is the ability to promptly and adequately determine and take actions to protect members of the public and emergency workers. Radiological accident assessment must take account of all critical information available at any time and must be an iterative and dynamic process aimed at reviewing the response as more detailed and complete information becomes available. This manual provides the tools, generic procedures and data needed for an initial response to a non-reactor radiological accident. This manual is one out of a set of IAEA publications on emergency preparedness and response, including Method for the Development of Emergency Response Preparedness for Nuclear or Radiological Accidents (IAEA-TECDOC-953), Generic Assessment Procedures for Determining Protective Actions During a Reactor Accident (IAEA-TECDOC-955) and Intervention Criteria in a Nuclear or Radiation Emergency (Safety Series No. 109)

  9. Estimation of dose in dental radiology exams in critical regions

    International Nuclear Information System (INIS)

    Bonzoumet, S.P.J.; Braz, D.; Padilha, Lucas

    2005-01-01

    The objective of this paper is to estimate the values of doses, which are absorbed dose to the lens and thyroid in a dental X-ray. Thermoluminescence dosimeters were used, once they provide a reading of quality and effectiveness. This study was based on dental exams conducted in patients in order to estimate the dose that disperses to the lens of the eye and for the thyroid during an intraoral exam. Data collection took place in two institutions, one governmental, which had the device SELETRONIC 70X and other particular. This study showed that there is a considerable variation between the appliances. Using the appliance DABI 1070, there was a greater absorption of radiation in the right eye (values greater than 5 mGy) and a lower dose in the thyroid, and the Seletronic 70X presented an incidence of higher dose deposited in the skin and in other points there was a balance in the values. In the appliance SELETRONIC 70X, there was again a greater absorption of radiation in the right eye and a lower setting in the thyroid. The excessive dose, besides does not favor at all for the quality of radiograph, represents a risk for the patient who absorbs unnecessary and harmful radiation to the body

  10. Assessment of radiological status of underground tunnel of radiochemistry wing

    International Nuclear Information System (INIS)

    Patre, D.K.; Thanamani, S.; Ojha, Shashikala; Murali, S.

    2012-01-01

    Radiochemistry Wing, RLG has design based safety systems for lab exhaust and glove box ventilation exhaust. The respective exhaust headers are routed from the lab exhaust point to the filter house. The concretized underground tunnel runs between Radiochemistry wing, RLG and Filter house about 100 m away. It houses the main exhaust tunnel made of MS, has reportedly developed leakage in the MS lines of exhaust due to ageing. It was indicated by the inadequate ventilation to the lab exhaust which reduced ∼ 10 % of the total exhaust. It was decided to carry out the replacement of main exhaust duct subject to radiological safety and clearance from the regulatory agencies. Since the duct had been in use since past 40 years, HP assessment on contamination status, clearance from local safety committee and related regulatory agency are mandatory. In view of the same, the study on radiological parameters was taken up and the paper describes the results of our radiological surveillance. Proposed replacement work involves approximately estimated surface area of duct as 520 m 2 , volume of the material as 106 m 3 and the weight of material of exhaust duct as 12.5 tons. Underground tunnel of radiochemistry wing consists of 3 main segments. It was monitored thoroughly by radiation survey. Spot air sample was collected during the radiological survey. Around 200 swipes were taken from various portions of the segments and the effluent pipelines. Last two tunnel segment were not approachable. Smear swipes were taken from top, side, bottom and floor of each segment. Calibrated scintillation counters were used for assessment of μ air activity and μ contamination check. Spot air samples were taken during different operations showed no activity. Dose rate in the tunnel was found to be less than 1 μSv/h (0.1 mR/h). The μ contamination levels were found in increasing order from the first segment to the last segment. (0.05 - 0.1 Bq/cm 2 ). Effluent pipelines were found to have

  11. Occupational dose assessment and national dose registry system in Iran

    International Nuclear Information System (INIS)

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

    2011-01-01

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

  12. An education and training programme for radiological institutes: impact on the reduction of the CT radiation dose

    International Nuclear Information System (INIS)

    Schindera, Sebastian T.; Allmen, Gabriel von; Vock, Peter; Szucs-Farkas, Zsolt; Treier, Reto; Trueb, Philipp R.; Nauer, Claude

    2011-01-01

    To establish an education and training programme for the reduction of CT radiation doses and to assess this programme's efficacy. Ten radiological institutes were counselled. The optimisation programme included a small group workshop and a lecture on radiation dose reduction strategies. The radiation dose used for five CT protocols (paranasal sinuses, brain, chest, pulmonary angiography and abdomen) was assessed using the dose-length product (DLP) before and after the optimisation programme. The mean DLP values were compared with national diagnostic reference levels (DRLs). The average reduction of the DLP after optimisation was 37% for the sinuses (180 vs. 113 mGycm, P < 0.001), 9% for the brain (982 vs. 896 mGycm, P < 0.05), 24% for the chest (425 vs. 322 mGycm, P < 0.05) and 42% for the pulmonary arteries (352 vs. 203 mGycm, P < 0.001). No significant change in DLP was found for abdominal CT. The post-optimisation DLP values of the sinuses, brain, chest, pulmonary arteries and abdomen were 68%, 10%, 20%, 55% and 15% below the DRL, respectively. The education and training programme for radiological institutes is effective in achieving a substantial reduction in CT radiation dose. (orig.)

  13. Preliminary characterization of dose in personnel of interventional radiology; Caracterizacao preliminar da dose em profissionais de radiologia intervencionista

    Energy Technology Data Exchange (ETDEWEB)

    Godolfim, Laura Larre; Anes, Mauricio; Bacelar, Alexandre; Lykawka, Rochelle [Hospital de Clinicas de Porto Alegre (HCPA), Porto Alegre, RS (Brazil)

    2016-07-01

    Exposure to X-rays of Interventional Radiology professionals (IR) impacts in the high dose rate received by these individuals, and there are reports of biological effects of this professional activity. Therefore, it is fomented greater control over the doses received by these workers. This research intends to characterize the doses received by the professionals during IR procedures. We evaluated the doses of radiologists, anesthesiologists and nursing staff of the Hospital de Clinicas de Porto Alegre, through measures with dosimeters of the OSL type, distributed in up to six regions of the body of these professionals. Until now were accompanied 33 cholangiography procedures and 29 embolization procedures. As a preliminary result, it was possible to identify a wide variation between doses of the professionals of the same function in each procedure. In overview, the dose of the professionals presented in descending order as a radiologist 1> radiologist 2 > anesthetist > nursing. (author)

  14. An Internal Dose Assessment Associated with Personal Food Intake

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Joeun; Jae, Moosung [Hanyang University, Seoul (Korea, Republic of); Hwang, Wontae [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    ICRP (International Commission on Radiological Protection), Therefore, had recommended the concept of 'Critical Group'. Recently the ICRP has recommended the use of 'Representative Person' on the new basic recommendation 103. On the other hand the U.S. NRC (Nuclear Regulatory Commission) has adopted more conservative concept, 'Maximum Exposed Individuals (MEI)' of critical Group. The dose assessment in Korea is based on MEI. Although dose assessment based on MEI is easy to receive the permission of the regulatory authority, it is not efficient. Meanwhile, the internal dose by food consumption takes an important part. Therefore, in this study, the internal dose assessment was performed in accordance with ICRP's new recommendations. The internal dose assessment was performed in accordance with ICRP's new recommendations. It showed 13.2% decreased of the annual internal dose due to gaseous effluents by replacing MEI to the concept of representative person. Also, this calculation based on new ICRP's recommendation has to be extended to all areas of individual dose assessment. Then, more accurate and efficient values might be obtained for dose assessment.

  15. Evaluating variability and uncertainty in radiological impact assessment using SYMBIOSE

    International Nuclear Information System (INIS)

    Simon-Cornu, M.; Beaugelin-Seiller, K.; Boyer, P.; Calmon, P.; Garcia-Sanchez, L.; Mourlon, C.; Nicoulaud, V.; Sy, M.; Gonze, M.A.

    2015-01-01

    SYMBIOSE is a modelling platform that accounts for variability and uncertainty in radiological impact assessments, when simulating the environmental fate of radionuclides and assessing doses to human populations. The default database of SYMBIOSE is partly based on parameter values that are summarized within International Atomic Energy Agency (IAEA) documents. To characterize uncertainty on the transfer parameters, 331 Probability Distribution Functions (PDFs) were defined from the summary statistics provided within the IAEA documents (i.e. sample size, minimal and maximum values, arithmetic and geometric means, standard and geometric standard deviations) and are made available as spreadsheet files. The methods used to derive the PDFs without complete data sets, but merely the summary statistics, are presented. Then, a simple case-study illustrates the use of the database in a second-order Monte Carlo calculation, separating parametric uncertainty and inter-individual variability. - Highlights: • Parametric uncertainty in radioecology was derived from IAEA documents. • 331 Probability Distribution Functions were defined for transfer parameters. • Parametric uncertainty and inter-individual variability were propagated

  16. Estimation of absorbed dose and its biological effects in subjects undergoing neuro interventional radiological procedures

    International Nuclear Information System (INIS)

    Basheerudeen, Safa Abdul Syed; Subramanian, Vinodhini; Venkatachalam, Perumal; Joseph, Santosh; Selvam, Paneer; Jose, M.T.; Annalakshmi, O.

    2016-01-01

    Radiological imaging has many applications due to its non-invasiveness, rapid diagnosis of life threatening diseases, and shorter hospital stay which benefit patients of all age groups. However, these procedures are complicated and time consuming, which use repeated imaging views and radiation, thereby increasing patient dose, and collective effective dose to the background at low doses. The effects of high dose radiation are well established. However, the effects of low dose exposure remain to be determined. Therefore, investigating the effect on medically exposed individuals is an alternative source to understand the low dose effects of radiation. The ESD (Entrance Surface Dose) was recorded using Lithium borate based TL dosimeters to measure the doses received by the head, neck and shoulder of the study subjects (n = 70) who underwent procedures like cerebral angiography, coiling, stenting and embolization

  17. Interactive Rapid Dose Assessment Model (IRDAM): user's guide

    International Nuclear Information System (INIS)

    Poeton, R.W.; Moeller, M.P.; Laughlin, G.J.; Desrosiers, A.E.

    1983-05-01

    As part of the continuing emphasis on emergency preparedness the US Nuclear Regulatory Commission (NRC) sponsored the development of a rapid dose assessment system by Pacific Northwest Laboratory (PNL). This system, the Interactive Rapid Dose Assessment Model (IRDAM) is a micro-computer based program for rapidly assessing the radiological impact of accidents at nuclear power plants. This User's Guide provides instruction in the setup and operation of the equipment necessary to run IRDAM. Instructions are also given on how to load the magnetic disks and access the interactive part of the program. Two other companion volumes to this one provide additional information on IRDAM. Reactor Accident Assessment Methods (NUREG/CR-3012, Volume 2) describes the technical bases for IRDAM including methods, models and assumptions used in calculations. Scenarios for Comparing Dose Assessment Models (NUREG/CR-3012, Volume 3) provides the results of calculations made by IRDAM and other models for specific accident scenarios

  18. Offsite dose calculation manual guidance: Standard radiological effluent controls for pressurized water reactors

    International Nuclear Information System (INIS)

    Meinke, W.W.; Essig, T.H.

    1991-04-01

    This report contains guidance which may be voluntarily used by licensees who choose to implement the provision of Generic Letter 89-01, which allows Radiological Effect Technical Specifications (RETS) to be removed from the main body of the Technical Specifications and placed in the Offsite Dose Calculation Manual (ODCM). Guidance is provided for Standard Effluent Controls definitions, Controls for effluent monitoring instrumentation, Controls for effluent releases, Controls for radiological environmental monitoring, and the basis for Controls. Guidance on the formulation of RETS has been available in draft from (NUREG-0471 and -0473) for a number of years; the current effort simply recasts those RETS into Standard Radiological Effluent Controls for application to the ODCM. Also included for completeness are: (1) radiological environmental monitoring program guidance previously which had been available as a Branch Technical Position (Rev. 1, November 1979); (2) existing ODCM guidance; and (3) a reproduction of generic Letter 89-01

  19. Proposal of dose constraint values to the patient in diagnostic radiology

    International Nuclear Information System (INIS)

    Arranz, L.; Sastre, J.M.; Ferrer, N.; Andres, J.C. De; Guibelalde, E.; Tobarra, B.; Madrid, G.

    1996-01-01

    A dose constraint is the value of an individual dose not to be exceeded in the individual dose distribution considered in an optimization process. The objective of a dose constraints is to set a ceiling to the doses to individual from a source, practice or task which are considered acceptable in the optimization process at the design stage. Implicitly, as C. Zuur states, dose constraints are below the relevant dose limit and usually should be established as local or national levels. Exposures for medical purposes are not subject to dose limits and hence dose constraints were recommended by the ICRP just for occupational and public exposures. However, as an effective tool for optimization for medical exposures, ICRP-60 in paragraph 180 recognizes the value of applying this concept to patient diagnostic radiology with some peculiarities: 'Considerations should be given to the use of dose constraints, or investigation levels, selected by the appropriate professional or regulatory agency, for application in some common diagnostic procedures. They should be applied with flexibility to allow higher cases where indicated by sound clinical judgement.' This paper analyzes retrospectively the dose levels imparted to patient in some common examinations (chest, lumbar spine and mammography) at different optimization stages of different facilities to propose some local constraints for diagnostic examinations. Dose values have been obtained under routine working conditions. Centres included in the survey have been chosen all over Spain, classifying them with particular attention to the following aspects: -Organizational aspects of the diagnostic radiology service, i.e., operational, technical and clinical criteria, as well as quality requirements. - Evaluation and revision of routine medical protocols. -Quality control of the radiological equipment. - Quality criteria for the surveillance of the weekly procedures, with requirements of proper training of die technical staff

  20. A Transparent Framework for guiding Radiological and Non-Radiological Contaminated Land Risk Assessments

    International Nuclear Information System (INIS)

    Lee, Alex; Mathers, Dan

    2003-01-01

    A framework is presented that may be used as a transparent guidance to both radiological and non-radiological risk assessments. This framework has been developed by BNFL, with external consultation, to provide a systematic approach for identifying key system drivers and to guide associated research packages in light of data deficiencies and sources of model uncertainty. The process presented represents an advance on existing working practices yet combines regulator philosophy to produce a robust, comprehensive, cost-effective and transparent work package. It aims at lending added confidence to risk models thereby adding value to the decision process

  1. Radiological Instrumentation Assessment for King County Wastewater Treatment Division

    International Nuclear Information System (INIS)

    Strom, Daniel J.; McConn, Ronald J.; Brodzinski, Ronald L.

    2005-01-01

    The King County Wastewater Treatment Division (WTD) have concern about the aftermath of a radiological dispersion event (RDE) leading to the introduction of significant quantities of radioactive material into its combined sanitary and storm sewer system. Radioactive material could come from the use of a radiological dispersion device (RDD). RDDs include 'dirty bombs' that are not nuclear detonations but are explosives designed to spread radioactive material. Radioactive material also could come from deliberate introduction or dispersion of radioactive material into the environment, including waterways and water supply systems. Volume 2 of PNNL-15163 assesses the radiological instrumentation needs for detection of radiological or nuclear terrorism, in support of decisions to treat contaminated wastewater or to bypass the West Point Treatment Plant (WPTP), and in support of radiation protection of the workforce, the public, and the infrastructure of the WPTP. Fixed radiation detection instrumentation should be deployed in a defense-in-depth system that provides (1) early warning of significant radioactive material on the way to the WPTP, including identification of the radionuclide(s) and estimates of the soluble concentrations, with a floating detector located in the wet well at the Interbay Pump Station and telemetered via the internet to all authorized locations; (2) monitoring at strategic locations within the plant, including (2a) the pipe beyond the hydraulic ram in the bar screen room; (2b) above the collection funnels in the fine grit facility; (2c) in the sampling tank in the raw sewage pump room; and (2d) downstream of the concentration facilities that produce 6% blended and concentrated biosolids. Engineering challenges exist for these applications. It is necessary to deploy both ultra-sensitive detectors to provide early warning and identification and detectors capable of functioning in high-dose rate environments that are likely under some scenarios

  2. Estimating effective dose to pediatric patients undergoing interventional radiology procedures using anthropomorphic phantoms and MOSFET dosimeters.

    Science.gov (United States)

    Miksys, Nelson; Gordon, Christopher L; Thomas, Karen; Connolly, Bairbre L

    2010-05-01

    The purpose of this study was to estimate the effective doses received by pediatric patients during interventional radiology procedures and to present those doses in "look-up tables" standardized according to minute of fluoroscopy and frame of digital subtraction angiography (DSA). Organ doses were measured with metal oxide semiconductor field effect transistor (MOSFET) dosimeters inserted within three anthropomorphic phantoms, representing children at ages 1, 5, and 10 years, at locations corresponding to radiosensitive organs. The phantoms were exposed to mock interventional radiology procedures of the head, chest, and abdomen using posteroanterior and lateral geometries, varying magnification, and fluoroscopy or DSA exposures. Effective doses were calculated from organ doses recorded by the MOSFET dosimeters and are presented in look-up tables according to the different age groups. The largest effective dose burden for fluoroscopy was recorded for posteroanterior and lateral abdominal procedures (0.2-1.1 mSv/min of fluoroscopy), whereas procedures of the head resulted in the lowest effective doses (0.02-0.08 mSv/min of fluoroscopy). DSA exposures of the abdomen imparted higher doses (0.02-0.07 mSv/DSA frame) than did those involving the head and chest. Patient doses during interventional procedures vary significantly depending on the type of procedure. User-friendly look-up tables may provide a helpful tool for health care providers in estimating effective doses for an individual procedure.

  3. Estimation of the genetically significant dose resulting from diagnostic radiology

    International Nuclear Information System (INIS)

    Angerstein, W.

    1978-01-01

    Based on the average gonad dose received per examination or per film and on the frequency of x-ray examinations (36 million per annum), the mean annual gonad dose to individuals in the GDR has been determined to be 33 mR. Considering different age groups of patients and the fact that the gonad dose to children is often significantly reduced in comparison to adults, estimates of the genetically significant dose (GSD) range from 7 to 19 mR per annum. Examinations of women have accounted for about 66 per cent of the GSD. The highest contribution to the GSD result from examinations of the following organs: kidneys, colon, bile duct (only in women), lumbar spine, pelois, hips, and proximal femur. Despite their high frequency, examinations of the stomach account for only about 3 per cent of the GSD. All thorax examinations (nearly 10,000,000 per annum) contribute less than 0.5 per cent, and the most frequent x-ray examinations of the skeletal system, skull, cervical spine, and teeth account for less than 3 per cent. The GSD values obtained are comparable with those from countries such as India, Japan, Netherlands, USSR, and USA. (author)

  4. Derivation of the source term, dose results and associated radiological consequences for the Greek Research Reactor – 1

    Energy Technology Data Exchange (ETDEWEB)

    Pappas, Charalampos, E-mail: chpappas@ipta.demokritos.gr; Ikonomopoulos, Andreas; Sfetsos, Athanasios; Andronopoulos, Spyros; Varvayanni, Melpomeni; Catsaros, Nicolas

    2014-07-01

    Highlights: • Source term derivation of postulated accident sequences in a research reactor. • Various containment ventilation scenarios considered for source term calculations. • Source term parametric analysis performed in case of lack of ventilation. • JRODOS employed for dose calculations under eighteen modeled scenarios. • Estimation of radiological consequences during typical and adverse weather scenarios. - Abstract: The estimated source term, dose results and radiological consequences of selected accident sequences in the Greek Research Reactor – 1 are presented and discussed. A systematic approach has been adopted to perform the necessary calculations in accordance with the latest computational developments and IAEA recommendations. Loss-of-coolant, reactivity insertion and fuel channel blockage accident sequences have been selected to derive the associated source terms under three distinct containment ventilation scenarios. Core damage has been conservatively assessed for each accident sequence while the ventilation has been assumed to function within the efficiency limits defined at the Safety Analysis Report. In case of lack of ventilation a parametric analysis is also performed to examine the dependency of the source term on the containment leakage rate. A typical as well as an adverse meteorological scenario have been defined in the JRODOS computational platform in order to predict the effective, lung and thyroid doses within a region defined by a 15 km radius downwind from the reactor building. The radiological consequences of the eighteen scenarios associated with the accident sequences are presented and discussed.

  5. Simulation-based computation of dose to humans in radiological environments

    Energy Technology Data Exchange (ETDEWEB)

    Breazeal, N.L. [Sandia National Labs., Livermore, CA (United States); Davis, K.R.; Watson, R.A. [Sandia National Labs., Albuquerque, NM (United States); Vickers, D.S. [Brigham Young Univ., Provo, UT (United States). Dept. of Electrical and Computer Engineering; Ford, M.S. [Battelle Pantex, Amarillo, TX (United States). Dept. of Radiation Safety

    1996-03-01

    The Radiological Environment Modeling System (REMS) quantifies dose to humans working in radiological environments using the IGRIP (Interactive Graphical Robot Instruction Program) and Deneb/ERGO simulation software. These commercially available products are augmented with custom C code to provide radiation exposure information to, and collect radiation dose information from, workcell simulations. Through the use of any radiation transport code or measured data, a radiation exposure input database may be formulated. User-specified IGRIP simulations utilize these databases to compute and accumulate dose to programmable human models operating around radiation sources. Timing, distances, shielding, and human activity may be modeled accurately in the simulations. The accumulated dose is recorded in output files, and the user is able to process and view this output. The entire REMS capability can be operated from a single graphical user interface.

  6. Simulation-based computation of dose to humans in radiological environments

    International Nuclear Information System (INIS)

    Breazeal, N.L.; Davis, K.R.; Watson, R.A.; Vickers, D.S.; Ford, M.S.

    1996-03-01

    The Radiological Environment Modeling System (REMS) quantifies dose to humans working in radiological environments using the IGRIP (Interactive Graphical Robot Instruction Program) and Deneb/ERGO simulation software. These commercially available products are augmented with custom C code to provide radiation exposure information to, and collect radiation dose information from, workcell simulations. Through the use of any radiation transport code or measured data, a radiation exposure input database may be formulated. User-specified IGRIP simulations utilize these databases to compute and accumulate dose to programmable human models operating around radiation sources. Timing, distances, shielding, and human activity may be modeled accurately in the simulations. The accumulated dose is recorded in output files, and the user is able to process and view this output. The entire REMS capability can be operated from a single graphical user interface

  7. Methodology for assessing the radiological impact on environment

    International Nuclear Information System (INIS)

    Zhang Yongxing

    1988-01-01

    During the 1940s, the early stages of nuclear programmes, the assessment of the radionuclides released to the environment was first initiated for the large nuclear facilities, with emphasis placed on environmental monitoring. The radiological assessment is a quantitative process of estimating the impact on human, resulting from the releases of the radionuclides to the environment. It is a multidisciplinary subject including identification of source terms, environmental transport and dispersion, health effect evaluation and so on. This paper briefly, but comprehensively, describes the methodology for the assessment of the environmental radiological consequence, and discusses the trend of various research fields related to the subject

  8. Assessment of Safety Parameters for Radiological Explosion Based on Gaussian Dispersion Model

    Energy Technology Data Exchange (ETDEWEB)

    Pandey, Alok [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Yu, Hyungjoon; Kim, Hong Suk [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2014-10-15

    These sources if used with explosive (called RDD - radiological dispersion device), can cause dispersion of radioactive material resulting in public exposure and contamination of the environment. Radiological explosion devices are not weapons for the mass destruction like atom bombs, but can cause the death of few persons and contamination of large areas. The reduction of the threat of radiological weapon attack by terrorist groups causing dispersion of radioactive material is one of the priority tasks of the IAEA Nuclear Safety and Security Program.Emergency preparedness is an essential part for reducing and mitigating radiological weapon threat. Preliminary assessment of dispersion study followed by radiological explosion and its quantitative effect will be helpful for the emergency preparedness team for an early response. The effect of the radiological dispersion depends on various factors like radioisotope, its activity, physical form, amount of explosive used and meteorological factors at the time of an explosion. This study aim to determine the area affected by the radiological explosion as pre assessment to provide feedback to emergency management teams for handling and mitigation the situation after an explosion. Most practical scenarios of radiological explosion are considered with conservative approach for the assessment of the area under a threat for emergency handling and management purpose. Radioisotopes under weak security controls can be used for a radiological explosion to create terror and socioeconomic threat for the public. Prior assessment of radiological threats is helpful for emergency management teams to take prompt decision about evacuation of the affected area and other emergency handling actions. Comparable activities of Co-60 source used in radiotherapy and Sr-90 source of disused and orphaned RTGs with two different quantities of TNT were used for the scenario development of radiological explosion. In the Basic Safety Standard (BSS

  9. Assessment of Safety Parameters for Radiological Explosion Based on Gaussian Dispersion Model

    International Nuclear Information System (INIS)

    Pandey, Alok; Yu, Hyungjoon; Kim, Hong Suk

    2014-01-01

    These sources if used with explosive (called RDD - radiological dispersion device), can cause dispersion of radioactive material resulting in public exposure and contamination of the environment. Radiological explosion devices are not weapons for the mass destruction like atom bombs, but can cause the death of few persons and contamination of large areas. The reduction of the threat of radiological weapon attack by terrorist groups causing dispersion of radioactive material is one of the priority tasks of the IAEA Nuclear Safety and Security Program.Emergency preparedness is an essential part for reducing and mitigating radiological weapon threat. Preliminary assessment of dispersion study followed by radiological explosion and its quantitative effect will be helpful for the emergency preparedness team for an early response. The effect of the radiological dispersion depends on various factors like radioisotope, its activity, physical form, amount of explosive used and meteorological factors at the time of an explosion. This study aim to determine the area affected by the radiological explosion as pre assessment to provide feedback to emergency management teams for handling and mitigation the situation after an explosion. Most practical scenarios of radiological explosion are considered with conservative approach for the assessment of the area under a threat for emergency handling and management purpose. Radioisotopes under weak security controls can be used for a radiological explosion to create terror and socioeconomic threat for the public. Prior assessment of radiological threats is helpful for emergency management teams to take prompt decision about evacuation of the affected area and other emergency handling actions. Comparable activities of Co-60 source used in radiotherapy and Sr-90 source of disused and orphaned RTGs with two different quantities of TNT were used for the scenario development of radiological explosion. In the Basic Safety Standard (BSS

  10. Commercial sugar, an alternative dosemeter for the dose determination in radiological emergency conditions

    International Nuclear Information System (INIS)

    Urena N, F.; Galindo, S.

    1997-01-01

    It was carried out the dosimetric evaluation of commercial sugar, with the purpose to determine the feasibility to be able to use this type of substance as a dosimetric material in cases to present some radiological emergency cases. The studied parameters using the Electron Paramagnetic Resonance (EPR) technique were: pre-doses signal or depth signal, dose-response stability, reproducibility, reliability and signal clearing decreasing. (Author)

  11. A review of occupational dose assessment uncertainties and approaches

    International Nuclear Information System (INIS)

    Anderson, R. W.

    2004-01-01

    The Radiological Protection Practitioner (RPP) will spend a considerable proportion of his time predicting or assessing retrospective radiation exposures to occupational personnel for different purposes. The assessments can be for a variety of purposes, such as to predict doses for occupational dose control, or project design purposes or to make retrospective estimates for the dose record, or account for dosemeters which have been lost or damaged. There are other less frequent occasions when dose assessment will be required such as to support legal cases and compensation claims and to provide the detailed dose information for epidemiological studies. It is important that the level of detail, justification and supporting evidence in the dose assessment is suitable for the requirements. So for instance, day to day operational dose assessments often rely mainly on the knowledge of the RPP in discussion with operators whilst at the other end of the spectrum a historical dose assessment for a legal case will require substantial research and supporting evidence for the estimate to withstand forensic challenge. The robustness of the assessment will depend on many factors including a knowledge of the work activities, the radiation dose uptake and field characteristics; all of which are affected by factors such as the time elapsed, the memory of operators and the dosemeters employed. This paper reviews the various options and uncertainties in dose assessments ranging from use of personal dosimetry results to the development of upper bound assessments. The level of assessment, the extent of research and the evidence adduced should then be appropriate to the end use of the estimate. (Author)

  12. Radiological passports as a decision support technique for post Chernobyl dose reduction in contaminated settlements

    International Nuclear Information System (INIS)

    Grebenkov, A.; Mansoux, H.; Yakushau, A.; Antsipov, G.; Averin, V.; Zhouchenko, Y.; Minenko, V.; Tirmarche, M.

    2004-01-01

    In 2000, IRSN and GRS initiated a support for collecting, securing and validating of existing data in the field of Chernobyl accident consequences and establishing a database including a detailed documentation in order to make available all reliable and objective information for decision makers, for planning of actions, for information of the public and for further scientific work. Three projects as a part of French/German Initiative (FGI) for humanitarian and technical assistance in favour of the Ukraine, Belarus and Russia have been established. The authors represent sub-project 3.9.1, which objectives are as follows: (i) develop and replenish the database for the Radiological-Hygienic Passports (RHP) and perform additional investigation of the target settlements in Belarus where comprehensive information has not been acquired yet, (ii) establish conditions and communication infrastructure for database availability, (iii) provide data analysis involving data on individual effective dose monitoring and results of countermeasures applied, and (iii) formulate the wider recommendations for the target settlements located in contaminated areas, concerning radiation, health, sanitary and social protection, countermeasures, industrial infrastructure development and reviving the local economy. During implementation of the project, 96 settlements with total population of 25 thousand were investigated and their RHPs were compiled. Every RHP consisted of 13 separate forms grouped under three principal headings: Statistics (societal and demographic structure of population, housing, land used and predominant soil type); Economical infrastructure and public utilities (farms, industries, schools, hospitals, shops, service, etc.); Radiological data and doses (total area subdivided vs. level of contamination, Cs-137 content in human body, contamination of agricultural products, contamination of households, annual effective dose). Every RHP was concluded with proposals as to the

  13. Cumulative radiation dose caused by radiologic studies in critically ill trauma patients.

    Science.gov (United States)

    Kim, Patrick K; Gracias, Vicente H; Maidment, Andrew D A; O'Shea, Michael; Reilly, Patrick M; Schwab, C William

    2004-09-01

    Critically ill trauma patients undergo many radiologic studies, but the cumulative radiation dose is unknown. The purpose of this study was to estimate the cumulative effective dose (CED) of radiation resulting from radiologic studies in critically ill trauma patients. The study group was composed of trauma patients at an urban Level I trauma center with surgical intensive care unit length of stay (LOS) greater than 30 days. The radiology records were reviewed. A typical effective dose per study for each type of plain film radiograph, computed tomographic scan, fluoroscopic study, and nuclear medicine study was used to calculate CED. Forty-six patients met criteria. The mean surgical intensive care unit and hospital LOS were 42.7 +/- 14.0 and 59.5 +/- 28.5 days, respectively. The mean Injury Severity Score was 32.2 +/- 15.0. The mean number of studies per patient was 70.1 +/- 29.0 plain film radiographs, 7.8 +/- 4.1 computed tomographic scans, 2.5 +/- 2.6 fluoroscopic studies, and 0.065 +/- 0.33 nuclear medicine study. The mean CED was 106 +/- 59 mSv per patient (range, 11-289 mSv; median, 104 mSv). Among age, mechanism, Injury Severity Score, and LOS, there was no statistically significant predictor of high CED. The mean CED in the study group was 30 times higher than the average yearly radiation dose from all sources for individuals in the United States. The theoretical additional morbidity attributable to radiologic studies was 0.78%. From a radiobiologic perspective, risk-to-benefit ratios of radiologic studies are favorable, given the importance of medical information obtained. Current practice patterns regarding use of radiologic studies appear to be acceptable.

  14. Modification of the radiological technique of Parma for reduction of irradiation dose

    Energy Technology Data Exchange (ETDEWEB)

    Stampfel, G.; Ionesco-Farco, F.

    1982-04-01

    A modified radiological technique to demonstrate the temporo-mandibular joint is presented. An ordinary X-ray tube put on the skin is directed 10/sup 0/ dorso-ventrally and 10/sup 0/ caudo-cranially to the temporo-mandibular joint. The irradiation skin dose applied is ten times smaller than by using the conventional contact technique.

  15. Federal Radiological Monitoring and Assessment Center (FRMAC), US response to major radiological accidents

    International Nuclear Information System (INIS)

    Mueller, P.G.

    2000-01-01

    radiological materials from: Nuclear Fuel Cycle Facilities, Space Craft Launches, Weapon (Department of Defence or DOE) Transportation, Weapon Production Facilities, Spacecraft Re-entry (domestic or foreign), Terrorist Incidents, High-Level Waste Transportation, Nuclear Power Plants. Key to the FRERP would be the establishment of the Federal Radiological Monitoring and Assessment Center (FRMAC). Development and implementation was assigned to DOE as the agency most capable of providing sufficient resources, assets, and support. In 1987, DOE subsequently assigned programmatic responsibility, with limited funding, to the Nevada Operations Office in Las Vegas, Nevada. (author)

  16. Teaching and Assessing Professionalism in Radiology Resident Education.

    Science.gov (United States)

    Kelly, Aine Marie; Gruppen, Larry D; Mullan, Patricia B

    2017-05-01

    Radiologists in teaching hospitals and in practices with residents rotating through are involved in the education of their residents. The Accreditation Council for Graduate Medical Education requires evidence that trainees are taught and demonstrate competency not only in medical knowledge and in patient care-the historic focus of radiology education-but also in the so-called non-interpretative core competencies, which include professionalism and interpersonal skills. In addition to accreditation agencies, the prominent assessment practices represented by the American Board of Radiology core and certifying examinations for trainees, as well as Maintenance of Certification for practitioners, are planning to feature more non-interpretative competency assessment, including professionalism to a greater extent. Because professionalism was incorporated as a required competency in medical education as a whole, more clarity about the justification and expected content for teaching about competence in professionalism, as well as greater understanding and evidence about appropriate and effective teaching and assessment methods, have emerged. This article summarizes justifications and expectations for teaching and assessing professionalism in radiology residents and best practices on how to teach and evaluate professionalism that can be used by busy radiology faculty in their everyday practice supervising radiology residents. Copyright © 2017 The Association of University Radiologists. Published by Elsevier Inc. All rights reserved.

  17. Radiation dose to patients from the coronary angiography and percutaneous transluminal coronary angioplasty in interventional radiology procedures

    International Nuclear Information System (INIS)

    Zheng, Jun-Zheng; Bai, Mei; Liu, Bin

    2008-01-01

    Full text: Objective: To survey and assess radiation dose to patients from coronary angiography (CA) and percutaneous transluminal coronary angioplasty (PTCA) in Beijing Xuanwu Hospital of Capital University of Medical Sciences. Methods: The dose-area product (DAP) values to the patient and cumulative dose (CD) were recorded from 84 coronary angiographies and 51 percutaneous transluminal coronary angioplasty. A Monte-Carlo based program PCXMC was used to calculate the effective dose from DAP values for each patient. Organ doses were also measured by thermoluminescent dosimeters (TLD) using a human-shaped phantom to compare the calculated organ dose from DAP. Results: The difference between the organ doses measured by TLDs and those from PCXMC software (P>0.05) were tolerable. The DAP value ranged from 7611∼60538 mGy·cm 2 for CA and 16423∼161973 mGy·cm 2 for PTCA. The effective dose for all procedures was determined to be in the range of 1.1∼6.9 mSv for CA and 2.3∼20.1 mSv for PTCA. CD ranged from 120.0 to 1016.0 mGy for CA and 287 to 2883 mGy for PTCA. Conversion factors between effective dose and DAP were 0.114∼0.139 mSv·Gy - 1·cm -2 for CA and 0.124∼0.142 mSv·Gy -1 ·cm -2 for PTCA; Conversion factors between organ dose and CD were derived for CA and PTCA, respectively. Conclusions: DAP and CD can be used as the dose indicator to calculate the organ dose and effective dose of patient based on Monte Carlo simulation. Using this method can provide important information of patient absorbed dose and enhance the radiation protection of patient in interventional radiology procedures. (author)

  18. Application study of RESRAD program in radiological impact assessment of very low level waste landfill

    International Nuclear Information System (INIS)

    Liu Aihua; Huang Dan; Jia Chuanzhao; Shen Haibo; Huang Kedong

    2014-01-01

    The radiological impact assessment of release utilizing a very low level waste landfill at home was carried out by using RESRAD program. The basic principles, sub-models and calculation method of RESRAD program were outlined. The selection and processing of site-specific parameters were analyzed. Selecting resident farmer scenario, the effective dose of the resident was calculated after the landfill was open, and the critical pathway as well as the critical nuclides was analyzed further. The results show that, for this landfill the maximum effective dose per year is 0.003 mSv, 0.13% of the average global public natural background radiation dose. There is small dose contribution for radioactive nuclides with short life, but large dose contribution for the nuclides with small retardation factor and middle or long-life. For the latter, the main exposure pathway is the underwater route, and enhancing indoor ventilation is an effective way to eliminate radiation dose of radon. (authors)

  19. Methodology for assessing the radiological consequences of radioactive releases from the BPX Facility at PPPL

    International Nuclear Information System (INIS)

    McKenzie-Carter, M.A.; Lyon, R.E.; Rope, S.K.

    1991-04-01

    This report contains information to support the Environmental Assessment for the Burning Plasma Experiment (BPX) Project proposed for the Princeton Plasma Physics Laboratory (PPPL). The assumptions and methodology used to assess the impact to members of the public from operational and accidental releases of radioactive material from the proposed BPX during the operational period of the project are described. A description of the tracer release tests conducted at PPPL by NOAA is included; dispersion values from these tests are used in the dose calculations. Radiological releases, doses, and resulting health risks are calculated and summarized. The computer code AIRDOS- EPA, which is part of the computer code system CAP-88, is used to calculate the individual and population doses for routine releases; FUSCRAC3 is used to calculate doses resulting from off-normal releases where direct application of the NOAA tracer test data is not practical. Where applicable, doses are compared to regulatory limits and guideline values. 48 refs., 16 tabs

  20. Quality assessment in radiological imaging methods

    International Nuclear Information System (INIS)

    Herstel, W.

    1985-01-01

    The equipment used in diagnostic radiology is becoming more and more complicated. In the imaging process four components are distinguished, each of which can introduce loss in essential information: the X-ray source, the human body, the imaging system and the observer. In nearly all imaging methods the X-ray quantum fluctuations are a limitation to observation. But there are also technical factors. As an illustration it is shown how in a television scanning process the resolution is restricted by the system parameters. A short review is given of test devices and the results are given of an image comparison based on regular bar patterns. Although this method has the disadvantage of measuring mainly the limiting resolution, the results of the test correlate reasonably well with the subjective appreciations of radiographs of bony structures made by a group of trained radiologists. Fluoroscopic systems should preferably be tested using moving structures under dynamic conditions. (author)

  1. Radiological Impacts Assessment during Normal Decommissioning Operation for EU-APR

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Do Hyun; Lee, Keun Sung [KHNP CRI, Daejeon (Korea, Republic of); Lee, ChongHui [KEPCO Engineering and Construction, Gimcheon (Korea, Republic of)

    2016-10-15

    In this paper, radiological impacts on human beings during normal execution of the decommissioning operations from the current standard design of EU-APR which has been modified and improved from its original design of APR1400 to comply with EUR, are evaluated. Decommissioning is the final phase in the life cycle of a nuclear installation, covering all activities from shutdown and removal of fissile material to environmental restoration of the site. According to article 5.4 specified in chapter 2.20 of European Utility Requirements (EUR), all relevant radiological impacts on human being should be considered during the environmental assessment of decommissioning, including external exposure from direct radiation of plant and other radiation sources, and internal exposure due to inhalation and ingestion. In this paper, radiological impacts on human beings during normal circumstances of the decommissioning operation were evaluated from the current standard design of EU-APR based on the simple transport model and practical generic methodology for assessing the radiological impact provided by IAEA. The results of dose assessment fulfilled the dose limit for all scenarios.

  2. Cursory radiological assessment: Battelle Columbus Laboratory Decommissioning and Decontamination Project

    International Nuclear Information System (INIS)

    Smith, W.H.; Munyon, W.J.; Mosho, G.D.; Robinet, M.J.; Wynveen, R.A.

    1988-10-01

    This document reports on the results obtained from a cursory radiological assessment of various properties at the Battelle Columbus Laboratory, Columbia, Ohio. The cursory radiological assessment is part of a preliminary investigation for the Battelle Columbus Laboratory Decommissioning and Decontamination Project. The radiological assessment of Battelle Columbus Laboratory's two sites included conducting interior and exterior building surveys and collecting and analyzing air, sewer system, and soil samples. Direct radiological surveys were made of floor, wall, and overhead areas. Smear surveys were made on various interior building surfaces as well as the exterior building vents. Air samples were collected in select areas to determine concentrations of Rn-222, Rn-220, and Rn-219 daughters, in addition to any long-lived radioactive particulates. Radon-222 concentrations were continuously monitored over a 24-hr period at several building locations using a radon gas monitoring system. The sanitary sewer systems at King Avenue, West Jefferson-North, and West Jefferson-South were each sampled at select locations. All samples were submitted to the Argonne Analytical Chemistry Laboratory for various radiological and chemical analyses. Environmental soil corings were taken at both the King Avenue and West Jefferson sites to investigate the potential for soil contamination within the first 12-inches below grade. Further subsurface investigations at the West Jefferson-North and West Jefferson-South areas were conducted using soil boring techniques. 4 refs., 10 figs., 10 tabs

  3. Radiological assessment of the radioactive wastes management

    International Nuclear Information System (INIS)

    Domenech Nieves, Haydee; Hernandez Saiz, Alejandro

    1996-01-01

    In the work are obtained the dose values resulting from the evaluation of the conditioning operations of wastes in the scenarios of exposure that are mentioned and are compared with the dose restriction suggested for the moment for such tasks. The radioactive wastes that are evaluated in the work are: liquids -both those from the generating institutions and the ones stored in the Managua- located deposit, Radon-226 not-in-use solids and sources 226: the results demonstrate that it is possible to treat in a year the total volume of the liquid and solid radioactive wastes as well as a large number of sources of Radon-226

  4. A probabilistic approach to Radiological Environmental Impact Assessment

    International Nuclear Information System (INIS)

    Avila, Rodolfo; Larsson, Carl-Magnus

    2001-01-01

    Since a radiological environmental impact assessment typically relies on limited data and poorly based extrapolation methods, point estimations, as implied by a deterministic approach, do not suffice. To be of practical use for risk management, it is necessary to quantify the uncertainty margins of the estimates as well. In this paper we discuss how to work out a probabilistic approach for dealing with uncertainties in assessments of the radiological risks to non-human biota of a radioactive contamination. Possible strategies for deriving the relevant probability distribution functions from available empirical data and theoretical knowledge are outlined

  5. Quality Control Assessment of Radiology Devices in Kerman Province, Iran

    OpenAIRE

    Zahra Jomehzadeh; Ali Jomehzadeh; Mohammad Bagher Tavakoli

    2016-01-01

    Introduction Application of quality control (QC) programs at diagnostic radiology departments is of great significance for optimization of image quality and reduction of patient dose. The main objective of this study was to perform QC tests on stationary radiographic X-ray machines, installed in 14 hospitals of Kerman province, Iran. Materials and Methods In this cross-sectional study, QC tests were performed on 28 conventional radiographic X-ray units in Kerman governmental hospitals, based ...

  6. Optimization of dose in computerized radiology exams of the hands

    International Nuclear Information System (INIS)

    Pavan, Ana Luiza Menegatti; Alvarez, Matheus; Alves, Allan Felipe Fattori; Dela Rosa, Maria Eugenia; Miranda, Jose Ricardo de Arruda

    2014-01-01

    Fractures and dislocations of the hand are some of the most frequently encountered injuries of the musculoskeletal system traumas. To evaluate these lesions radiography is the investigation of choice, and is rarely needed the help of other images to establish the diagnosis and treatment. The image quality of the X-ray examination is therefore essential. In this study a homogeneous phantom hand was developed for use in the hand image optimization process. In this procedure were quantified for different tissue thicknesses which are an anthropomorphic hand phantom. To perform the classification and quantification of tissue was applied membership functions in histograms of CT scans. The same procedure was adopted for 30 retrospective examinations of patients in the Hospital of the Faculty of Medicine of Botucatu UNESP (HCFMB-UNESP). The homogeneous phantom built was used to calibrate the techniques used in clinical routine (RC). Such calibrated techniques were used to acquire images of anthropomorphic phantom. These images were analyzed by Visual Grading Method (VFA) by experienced radiologists in the area. The image with better grade in AGV and lower dose was chosen as the Gold Standard. The results showed concordance between the tissue thicknesses which constitute the anthropomorphic phantom and the sample evaluated patients, with variations between 12.63% and 6.48% for soft tissue and bone, respectively. The Gold Technical Standard compared with the technique normally used in the CR reduces dose charge 41.28% and 33.18% in the tube

  7. Northern Marshall Islands radiological survey: radionuclide concentrations in fish and clams and estimated doses via the marine pathway

    International Nuclear Information System (INIS)

    Robison, W.L.; Noshkin, V.E.; Phillips, W.A.; Eagle, R.J.

    1981-01-01

    The survey consisted, in part, of an aerial radiological reconnaissance to map the external gamma-ray exposure rates. As a secondary phase, terrestrial and marine samples were collected to assess the radiological dose from pertinent food chains to atoll inhabitants. The marine sample collection, processing, and dose assessment methodology are presented as well as the concentration data for 90 Sr, 137 Cs, 238 Pu, 239+240 Pu, 241 Am, and any of the other gamma emitters in fish and clam muscle tissue from the different species collected. Doses are calculated from the average radionuclide concentrations in fish and clam muscle tissue assuming an average daily intake of 200 and 10 g, respectivelty. The 90 Sr concentration in muscle tissue is very low and there is little difference in the average concentrations from the different fish from different atolls or islands. The 239+240 Pu concentration in the muscle tissue of all reef species, however, is higher than that in pelagic lagoon fish. In contrast, 137 Cs concentrations are lowest in the muscle tissue of the bottom-feeding reef species and highest in pelagic logoon fish. Recent measurements of radionuclide concentrations in fish muscle tissue and other marine dietary items from international sources show that the average concentrations in species from the Marshall Islands are comparable to those in fish typically consumed as food in the United States and are generally lower than those in most international marine dietary items. The whole-body dose rates based on continuous consumption of 200 g/d of fish range from 0.028 to 0.1 mrem/y; the bone-marrow dose rates range from 0.029 to 0.12 mrem/y. The dose commitment, or 30-y integral doses, range from 0.00063 to 0.0022 rem for the whole body and from 0.00065 to 0.0032 rem for the bone marrow

  8. A comparison of radiological risk assessment methods for environmental restoration

    International Nuclear Information System (INIS)

    Dunning, D.E. Jr.; Peterson, J.M.

    1993-01-01

    Evaluation of risks to human health from exposure to ionizing radiation at radioactively contaminated sites is an integral part of the decision-making process for determining the need for remediation and selecting remedial actions that may be required. At sites regulated under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), a target risk range of 10 -4 to 10 -6 incremental cancer incidence over a lifetime is specified by the US Environmental Protection Agency (EPA) as generally acceptable, based on the reasonable maximum exposure to any individual under current and future land use scenarios. Two primary methods currently being used in conducting radiological risk assessments at CERCLA sites are compared in this analysis. Under the first method, the radiation dose equivalent (i.e., Sv or rem) to the receptors of interest over the appropriate period of exposure is estimated and multiplied by a risk factor (cancer risk/Sv). Alternatively, incremental cancer risk can be estimated by combining the EPA's cancer slope factors (previously termed potency factors) for radionuclides with estimates of radionuclide intake by ingestion and inhalation, as well as radionuclide concentrations in soil that contribute to external dose. The comparison of the two methods has demonstrated that resulting estimates of lifetime incremental cancer risk under these different methods may differ significantly, even when all other exposure assumptions are held constant, with the magnitude of the discrepancy depending upon the dominant radionuclides and exposure pathways for the site. The basis for these discrepancies, the advantages and disadvantages of each method, and the significance of the discrepant results for environmental restoration decisions are presented

  9. Workplace-based assessment in radiology-where to now?

    International Nuclear Information System (INIS)

    Augustine, K.; McCoubrie, P.; Wilkinson, J.R.; McKnight, L.

    2010-01-01

    Assessment of doctors is in a state of flux. Traditional methods of assessment have been critically examined and found inherently limited. The wholesale shift towards outcome-orientated education in the last 10 years has led to the relatively rapid development of a radically different method of assessment. This method focuses on assessing what doctors do in everyday practice rather than written or practical simulations. Known collectively as 'workplace-based assessment' tools, these have been embraced in North America, whereas they have been more cautiously adopted in the UK. However, many of these assessment tools have not been rigorously studied and, moreover, few have been specifically developed for assessing radiologists. However, they are likely to be incorporated into radiology training in the near future. This paper critically analyses both the underpinning assumptions behind this method and the evidence behind existing tools, and looks at the work that is required to develop, adopt or adapt such tools for use in radiology.

  10. Development of a Real-time Hand Dose Monitor for Personnel in Interventional Radiology

    Energy Technology Data Exchange (ETDEWEB)

    Ban, N.; Nakaoka, H.; Haruta, R.; Murakami, Y.; Kubo, T.; Maeda, T.; Kusama, T

    2001-07-01

    Medical procedures denoted as interventional radiology require operation near an X ray beam, which brings high dose exposures to the operators' hands. For the effectual control of their extremity doses, a prototype of a real-time wrist dosemeter has been developed, hand dose monitor (HDM), based on a single silicon detector. Experiments were performed to test its response to diagnostic X rays. The HDM was highly sensitive and showed a linear response down to doses of a few tens of microsieverts. Though dose rate, energy and angular dependence of the response were observed in some extreme conditions, the HDM was proved to be of practical use if it was appropriately calibrated. Since an HDM enables personnel to check their hand doses on a real-time basis, it would enable medical staff to control the exposure themselves. (author)

  11. Measurements of eye lens doses in interventional radiology and cardiology: Final results of the ORAMED project

    International Nuclear Information System (INIS)

    Vanhavere, F.; Carinou, E.; Domienik, J.; Donadille, L.; Ginjaume, M.; Gualdrini, G.; Koukorava, C.; Krim, S.; Nikodemova, D.; Ruiz-Lopez, N.; Sans-Merce, M.; Struelens, L.

    2011-01-01

    Within the ORAMED project (Optimization of Radiation Protection of Medical Staff) a coordinated measurement program for occupationally exposed medical staff was performed in different hospitals in Europe ( (www.oramed-fp7.eu)). The main objective was to obtain a set of standardized data on extremity and eye lens doses for staff involved in interventional radiology and cardiology and to optimize radiation protection. Special attention was given to the measurement of the doses to the eye lenses. In this paper an overview will be given of the measured eye lens doses and the main influence factors for these doses. The measured eye lens doses are extrapolated to annual doses. The extrapolations showed that monitoring of the eye lens should be performed on routine basis.

  12. Pilot study of the dose in crystalline lens in the interventional radiology practice

    International Nuclear Information System (INIS)

    Castro, A.; Martinez, A.; Fernandez, A.; Molina, D.; Sanchez, L.; Diaz, A.

    2014-08-01

    The interventional radiology involves considerable exposure levels for the occupationally exposed personnel (OEP). The doses can encompass a wide range of values in dependence of the function that develops the personnel and the complexity of each procedure. In organs like the crystalline lens and skin values can be reached that imply the appearance of deterministic effects if is not fulfilled the appropriate measures of radiological protection. This has been demonstrated through multiple studies, among those that the retrospective study of damages in the crystalline lens and dose has been one of those most commented, known as RELID. The objective of that study was to examine the opacity prevalence in the crystalline lens in workers linked to the interventional cardiology and to correlate it with the occupational exposition. The obtained results contributed to that the ICRP recommend a new limit value of equivalent dose for crystalline lens of 20 mSv in one year. With the objective of analyzing the operational implications, in the radiological surveillance programs that they could originate with the new recommendations was developed a pilot study to evaluate the dose in crystalline lens in the OEP linked to the interventional radiology in a Cuban hospital. For this, an anthropomorphic mannequin RANDO-ALDERSON was used on which thermoluminescent dosimeters were placed below and above of the leaded apron and in different positions at level of the crystalline lens: above, below and to the sides of the leaded lenses that the personnel uses routinely. The mannequin was located on the same positions that occupy the main specialist that execute the procedure, as well as of the nurse to assist him. The measurements were made simulating the more representative procedures about complexity, duration time and exposure rate. The used dosimeters were RADOS model for whole body composed of two thermoluminescent detectors Gr-200 (LiF: Mg, Cu, P) to evaluate personal equivalent dose

  13. Analysis of dose to crystalline in Interventional radiology: a purpose of one case

    International Nuclear Information System (INIS)

    Carrera M, F.; Moreno R, F.; Velazquez M, F.; Manzano M, F.J.; Moreno S, T.

    1998-01-01

    The present work shows the dose values to crystalline for the personnel which works in interventional radiology procedures. It was took data of 436 studies with a total of 2,133.4 minutes in fluoroscopy and 19,563 images. It was showed dose values to crystalline in three situations: without blinding, with blinding of 0.25 and 0.50 mm Pb and by type of study: fluoroscopy, graphie and total. The dose means and ranges to patient for each of these studies also are detailed. (Author)

  14. The establishment and use of dose reference levels in general paediatric radiology

    International Nuclear Information System (INIS)

    Marsden, P.J.; Hardwick, J.; Mencik, C.; McLaren, C.; Young, C.; Mashford, P.

    2001-01-01

    Diagnostic reference levels for general paediatric radiology have been established in terms of delivered exposure parameters rather than skin dose or dose-area product. With supporting measurements from equipment quality assurance and assumptions of standard patient sizes it was possible to derive reference levels in terms of entrance surface dose. This allowed comparison to be made with other published data. The reference levels for common examinations are presented for different age bands. There is a notable variation with patient age for some examinations which is not apparent in other published data. (author)

  15. Radiology education. The evaluation and assessment of clinical competence

    International Nuclear Information System (INIS)

    Hibbert, Kathryn M.; Van Deven, Teresa; Chhem, Rethy K.; Nagasaki Univ.; Wang, Shih-chang; Royal Australian and New Zealand College of Radiologists, Sydney

    2012-01-01

    Third volume of a trilogy devoted to radiology education and improvement of medical imaging students' learning, teaching, and scholarship. Reviews the philosophies, theories, and principles that underpin assessment and evaluation in radiology education. Includes a series of rich case studies. Written by an international group of experienced educators and medical professionals. This book reviews the philosophies, theories, and principles that underpin assessment and evaluation in radiology education, highlighting emerging practices and work done in the field. The sometimes conflicting assessment and evaluation needs of accreditation bodies, academic programs, trainees, and patients are carefully considered. The final section of the book examines assessment and evaluation in practice, through the development of rich case studies reflecting the implementation of a variety of approaches. This is the third book in a trilogy devoted to the scholarship of radiology education and is the culmination of an important initiative to improve medical imaging students' learning, teaching, and scholarship by bringing together experienced educators and medical professionals. The previous two books focused on the culture and the learning organizations in which our future radiologists are educated and on the application of educational principles in the education of radiologists. Here, the trilogy comes full circle: attending to the assessment and evaluation of the education of its members has much to offer back to the learning of the organization.

  16. Radiological/toxicological sabotage assessments at the Savannah River Site

    International Nuclear Information System (INIS)

    Johnson, H.D.; Pascal, M.D.; Richardson, D.L.

    1995-01-01

    This paper describes the methods being employed by Westinghouse Savannah River Company (WSRC) to perform graded assessments of radiological and toxicological sabotage vulnerability at Savannah River Site (SRS) facilities. These assessments are conducted to ensure that effective measures are in place to prevent, mitigate, and respond to a potential sabotage event which may cause an airborne release of radiological/toxicological material, causing an adverse effect on the health and safety of employees, the public, and the environment. Department of Energy (DOE) Notice 5630.3A, open-quotes Protection of Departmental Facilities Against Radiological and Toxicological Sabotage,close quotes and the associated April 1993 DOE-Headquarters guidance provide the requirements and outline an eight-step process for hazardous material evaluation. The process requires the integration of information from a variety of disciplines, including safety, safeguards and security, and emergency preparedness. This paper summarizes WSRC's approach towards implementation of the DOE requirements, and explains the inter-relationships between the Radiological and Toxicological Assessments developed using this process, and facility Hazard Assessment Reports (HAs), Safety Analysis Reports (SARs), and Facility Vulnerability Assessments (VAs)

  17. Dose and risk evaluation to the thyroid gland in intra-oral dental radiology

    International Nuclear Information System (INIS)

    Souza, Edmilson M.; Lima, Marco A.F.; Kelecom, Alphonse; Correa, Samanda C.A.; Silva, Ademir X.; Brito, Alan

    2008-01-01

    Intra-oral technique is one of the most frequently used procedures of dental radiology, allowing the detection of a variety of dental anomalies such as caries, dental trauma and periodontal lesions, while exposing patients to relatively low doses of radiation. However, although the adverse effects of doses generated by dental radiology are essentially stochastic, a number of epidemiological studies have provided evidence of an increased risk of thyroid tumors for dental radiography. Many studies have measured doses of radiation for dental radiography, but only a few have estimated thyroid dose. Furthermore, most of the studies on dose evaluation in dental radiology are based on standardized calculation phantoms, which neglect the variance of the patient size or even sex. The purpose of this study is to use the Monte Carlo code MCNPX and the FAX (Female Adult voXel) and MAX (Male Adult voXel) phantoms to investigate how absorbed doses to the thyroid gland in intraoral dental examinations vary in female and male patients. The lifetime cancer incidence attributable to dental examinations were estimated using the Biological Effects of Ionizing Radiations (BEIR) VII Committee Report. The phantoms study proved a useful trial for detecting the radiation dose to the thyroid gland and conclusively supported that the anatomy may be regarded as an influencing factor in radiation dose received during dental examination. Finally, the results have also confirmed that the association of the MCNPX code and the MAX and FAX phantoms is very useful in dosimetric studies on radiographic examinations of female and male patients. (author)

  18. Radiologic techniques and changes in exposure doses to patients

    International Nuclear Information System (INIS)

    Suzuki, Shoichi; Orito, Takeo; Fujii, Shigehisa; Ishizaka, Masatsuna; Takeuchi, Akira; Koga, Sukehiko

    1990-01-01

    A survey questionnaire was sent to 200 randomly selected hospitals in Japan, and 118 hospitals (59.5%) responded. The results were compared with those of the similar surveys performed in 1973 (1973's survey) and 1979 (1979's survey). According to plain radiography, obstetric radiography, infantile radiography, and mammography, the following items were surveyed: tube voltage, tube current, and exposure time; intensifying screen and kinds of film; grid ratio; added filter; and focus-film distance. Average tube voltage was almost the same as that in the 1979's survey, except for the high voltage radiography for the chest. The usage of both green fluororescence intensifying screen and orthofilm increased in number, as compared with that in the previous two surveys. The grid ratio of 8:1 was found to be more frequently used in the present survey than the previous two surveys. Focus-film distance for the breast varied widely (30-100 cm), which was similar to that in the 1979's survey. In the present survey, a distance of 100 cm in infantile radiography for the chest was seen in 27.5%, as compared with 41.2% in the 1979's survey. A distance of 150-200 cm was also found to be used. The present survey revealed exposure doses to be decreased by 56% as compared with the 1973's survey and by 39% as compared with the 1979's survey. (N.K.)

  19. Patient dose during radiological examination in the follow-up of bariatric surgery

    International Nuclear Information System (INIS)

    Moro, L.; Cazzani, C.; Tomarchio, O.; Morone, G.; Catona, A.; Fantinato, D.

    2007-01-01

    A patient dose survey was carried out measuring the kerma-area product (KAP) values during radiological evaluation in the follow-up of bariatric surgery. The procedures were performed by three radiologists to adjust laparoscopic gastric bands and to detect postoperative complications after Roux-en-Y gastric bypass procedures to treat morbid obesity. Total fluoroscopy time, exposure factors and the overall contribution of fluoroscopy to the accumulated KAP value were recorded. The median KAP values were used to estimate organ doses and effective dose to a standard patient; the radiation risk associated with the procedures was also evaluated. The doses were smaller for one of the three radiologists, owing to a more appropriate beam collimation and a reduction of the screening time. The KAP values ranged from 1.6 to 7.1 Gy cm 2 for the laparoscopic adjustable gastric banding management, and from 3.0 and 8.3 Gy cm 2 for the radiological examinations after gastric bypass. As a whole, the effective doses associated to these procedures were between 0.5 and 2.7 mSv. The organs receiving the highest doses were not only breast, stomach, pancreas and liver, but also lungs, owing to of their high radiosensitivity, significantly contributed to the effective dose. (authors)

  20. Documentation of in-training assessment for radiology trainees

    International Nuclear Information System (INIS)

    Long, Gillian

    2001-01-01

    AIM: To determine if the assessment of radiology trainees can be improved by modifying the in-training assessment form issued by the Royal College of Radiologists (RCR). MATERIALS AND METHODS: A qualitative study comparing the RCR assessment form with other alternative forms in use in the U.K. Individual semi-structured interviews were conducted with trainees (21) and trainers (18) in Sheffield to collect their views on the RCR form and an alternative form introduced on the North Trent Training Scheme. A postal questionnaire was sent to Heads of Training (24) to find out what assessment forms were in use at other centres and collect their views on the different forms. RESULTS: Trainees and trainers in Sheffield were virtually unanimous in their support of the new North Trent assessment form. The main advantages perceived were the encouragement of appraisal, setting of objectives and feedback from the trainees. Six other radiology training centres were using alternative assessment forms and all believed their forms had advantages over the RCR in-training assessment form. CONCLUSION: The results of this study suggest that the assessment process for radiology trainees can be improved by modifications to the RCR in-training assessment form and allows various recommendations to be made. Long, G. (2001)

  1. The current contribution of diagnostic radiology to the population dose in Great Britain

    International Nuclear Information System (INIS)

    Wall, B.F.; Rae, S.; Kendall, G.M.; Darby, S.C.; Fischer, E.S.; Harries, S.V.

    1980-01-01

    The National Radiological Protection Board of the UK has just completed a national survey to determine the genetically significant dose (GSD) to the population of Great Britain from diagnostic radiology. A statistically selected sample of about 80 hospitals spread throughout England, Scotland and Wales has supplied information on the numbers of patients examined in their X-ray departments during a week in June 1977, together with details of age, sex and examination technique. This sample is sufficient to make a reliable estimate of the total diagnostic work-load in all National Health Service Hospitals throughout Great Britain for a year. Gonadal doses from 16 examination types that are likely to be the main contributors to the GSD have been measured on nearly 5000 patients at 20 hospitals throug'out the country using specially developed thermoluminescent dosemeters. These gonadal doses are combined with the examination frequency figures and current values for child expectancy derived from data supplied by tthe registrar general, to estimate the GSD. Those changes in practice which have occurred since the late 1950's which may have influenced the new value for the GSD are discussed, as well as the progress that has been made in estimating population somatic doses from diagnostic radiology using clinical measurements that are currently underway. (H.K.)

  2. Radiological protection criteria risk assessments for waste disposal options

    International Nuclear Information System (INIS)

    Hill, M.D.

    1982-01-01

    Radiological protection criteria for waste disposal options are currently being developed at the National Radiological Protection Board (NRPB), and, in parallel, methodologies to be used in assessing the radiological impact of these options are being evolved. The criteria and methodologies under development are intended to apply to all solid radioactive wastes, including the high-level waste arising from reprocessing of spent nuclear fuel (because this waste will be solidified prior to disposal) and gaseous or liquid wastes which have been converted to solid form. It is envisaged that the same criteria will be applied to all solid waste disposal options, including shallow land burial, emplacement on the ocean bed (sea dumping), geological disposal on land and sub-seabed disposal

  3. Radiology

    International Nuclear Information System (INIS)

    Sykora, A.

    2006-01-01

    In this text-book basic knowledge about radiology, biomedical diagnostic methods (radiography, computer tomography), nuclear medicine and safety and radiation protection of personnel on the radiodiagnostic place of work are presented

  4. JUSTIFICATION FOR THE RADIOLOGICAL CRITERIA FOR THE USE OF AREAS WITH RESIDUAL RADIOACTIVE CONTAMINATION BASED ON THE DOSE APPROACH

    Directory of Open Access Journals (Sweden)

    V. Yu. Golikov

    2017-01-01

    Full Text Available The article presents a methodology for assessing the radiological criteria for the use of the territory (a land plot with buildings with residual radioactive contamination from the so-called “green area”, i.e., complete release from radiation control until a number of restrictions are imposed on the use of the territory. In accordance with the further use of the territory, a range of scenarios and pathways for the exposure of the population was considered. A set of models and their parameters, corresponding to the number of the considered pathways of exposure, was defined. Assuming a uniform distribution of a radionuclide with a unit concentration in the source zone, the distribution of effective doses for the population living in the territory with the residual radioactive contamination for different irradiation scenarios was calculated by stochastic modeling, 95% of the quantile of which was attributed to the dose in the representatives of the critical population group. Next, the value of radiological criteria, depending on the implemented scenario, was determined as the ratio of the dose constraint EL = 0,3 mSv/yr and 95% quantile in the distribution of the effective dose from a unit contamination. The numerical values of radiological criteria for the presence of radionuclides in the soil are presented, both for the radiation scenarios that correspond to the permanent residence of the population in the contaminated territory and for recreational use. A further consideration is given to the so-called worker scenario, which corresponds to the limited time spent on the contaminated territory and the simultaneous effects of radionuclides contained both in the soil and in the construction of the buildings. A comparison of the results of the own calculations with the data of other authors was carried out.

  5. Radionuclide transport and dose assessment modelling in biosphere assessment 2009

    International Nuclear Information System (INIS)

    Hjerpe, T.; Broed, R.

    2010-11-01

    Following the guidelines set forth by the Ministry of Trade and Industry (now Ministry of Employment and Economy), Posiva is preparing to submit a construction license application for the final disposal spent nuclear fuel at the Olkiluoto site, Finland, by the end of the year 2012. Disposal will take place in a geological repository implemented according to the KBS-3 method. The long-term safety section supporting the license application will be based on a safety case that, according to the internationally adopted definition, will be a compilation of the evidence, analyses and arguments that quantify and substantiate the safety and the level of expert confidence in the safety of the planned repository. This report documents in detail the conceptual and mathematical models and key data used in the landscape model set-up, radionuclide transport modelling, and radiological consequences analysis applied in the 2009 biosphere assessment. Resulting environmental activity concentrations in landscape model due to constant unit geosphere release rates, and the corresponding annual doses, are also calculated and presented in this report. This provides the basis for understanding the behaviour of the applied landscape model and subsequent dose calculations. (orig.)

  6. Perspectives on dosimetric uncertainties and radiological assessments of radioactive waste management

    International Nuclear Information System (INIS)

    Smith, G.M.; Pinedo, P.; Cancio, D.

    1997-01-01

    The purpose of this paper is to raise some issues concerning uncertainties in the estimation of doses of ionizing radiation arising from waste management practices and the contribution to those uncertainties arising from dosimetry modelling. The intentions are: (a) to provide perspective on the relative uncertainties in the different aspects of radiological assessments of waste management; (b) to give pointers as to where resources could best be targeted as regards reduction in overall uncertainties; and (c) to provide regulatory insight to decisions on low dose management as related to waste management practices. (author)

  7. Significance and principles of the calculation of the effective dose equivalent for radiological protection of personnel and patients

    International Nuclear Information System (INIS)

    Drexler, G.; Williams, G.

    1985-01-01

    The application of the effective dose equivalent, Hsub(E), concept for radiological protection assessments of occupationally exposed persons is justifiable by the practicability thus achieved with regard to the limiting principles. Nevertheless, it would be proper logic to further use as the basic limiting quantity the real physical dose equivalent of homogeneous whole-body exposure, and for inhomogeneous whole-body irradiation the Hsub(E) value, calculated by means of the concept of the effective dose equivalent. For then the required concepts, models and calculations would not be connected with a basic radiation protection quantity. Application of the effective dose equivalent for radiation protection assessments for patients is misleading and is not practical with regard to assessing an individual or collective radiation risk of patients. The quantity of expected harm would be better suited to this purpose. There is no need to express the radiation risk by a dose quantity, which means careless handling of good information. (orig./WU) [de

  8. Foetal Radiation Dose and Risk from Diagnostic Radiology Procedures: A Multinational Study

    International Nuclear Information System (INIS)

    Osei, Ernest K.; Darko, Johnson

    2012-01-01

    In diagnostic radiology examinations there is a benefit that the patient derives from the resulting diagnosis. Given that so many examinations are performed each year, it is inevitable that there will be occasions when an examination(s) may be inadvertently performed on pregnant patients or occasionally it may become clinically necessary to perform an examination(s) on a pregnant patient. In all these circumstances it is necessary to request an estimation of the foetal dose and risk. We initiated a study to investigate fetal doses from different countries. Exposure techniques on 367 foetuses from 414 examinations were collected and investigated. The FetDoseV4 program was used for all dose and risk estimations. The radiation doses received by the 367 foetuses ranges: <0.001–21.9 mGy depending on examination and technique. The associated probability of induced hereditary effect ranges: <1 in 200000000 (5 × 10 −9 ) to 1 in 10000 (1 × 10 −4 ) and the risk of childhood cancer ranges <1 in 12500000 (8 × 10 −8 ) to 1 in 500 (2 × 10 −3 ). The data indicates that foetal doses from properly conducted diagnostic radiology examinations will not result in any deterministic effect and a negligible risk of causing radiation induced hereditary effect in the descendants of the unborn child

  9. Handbook of selected organ doses for projections common in pediatric radiology

    International Nuclear Information System (INIS)

    Rosenstein, M.; Beck, T.J.; Warner, G.G.

    1979-05-01

    This handbook contains data from which absorbed dose (mrad) to selected organs can be estimated for common projections in pediatric radiology. The organ doses are for three reference patients: a newborn (0 to 6 months), a 1-year old child, and a 5-year old child. One intent of the handbook is to permit the user to evaluate the effect on organ dose to these reference pediatric patients as a function of certain changes in technical parameters used in or among facilities. A second intent is to permit a comparison to be made of organ doses as a function of age. This comparison can be extended to a reference adult by referring to the previous Handbook of Selected Organ Doses fo Projections Common in Diagnostic Radiology, FDA 76-8031. Assignment of organ doses to individual pediatric patients using the Handbook data is not recommended unless the physical characteristics of the patient closely correlate with one of the three reference pediatric patients given in Appendix A

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

    International Nuclear Information System (INIS)

    Vanhavere, F.

    2007-01-01

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

  11. Characterization of a MOSkin detector for in vivo skin dose measurements during interventional radiology procedures

    Energy Technology Data Exchange (ETDEWEB)

    Safari, M. J.; Wong, J. H. D.; Ng, K. H., E-mail: ngkh@um.edu.my [Department of Biomedical Imaging, Faculty of Medicine, University of Malaya, Kuala Lumpur 50603, Malaysia and University of Malaya Research Imaging Centre, Faculty of Medicine, University of Malaya, Kuala Lumpur 50603 (Malaysia); Jong, W. L. [Clinical Oncology Unit, Faculty of Medicine, University of Malaya, Kuala Lumpur 50603 (Malaysia); Cutajar, D. L.; Rosenfeld, A. B. [Centre for Medical Radiation Physics, University of Wollongong, Wollongong, NSW 2522 (Australia)

    2015-05-15

    Purpose: The MOSkin is a MOSFET detector designed especially for skin dose measurements. This detector has been characterized for various factors affecting its response for megavoltage photon beams and has been used for patient dose measurements during radiotherapy procedures. However, the characteristics of this detector in kilovoltage photon beams and low dose ranges have not been studied. The purpose of this study was to characterize the MOSkin detector to determine its suitability for in vivo entrance skin dose measurements during interventional radiology procedures. Methods: The calibration and reproducibility of the MOSkin detector and its dependency on different radiation beam qualities were carried out using RQR standard radiation qualities in free-in-air geometry. Studies of the other characterization parameters, such as the dose linearity and dependency on exposure angle, field size, frame rate, depth-dose, and source-to-surface distance (SSD), were carried out using a solid water phantom under a clinical x-ray unit. Results: The MOSkin detector showed good reproducibility (94%) and dose linearity (99%) for the dose range of 2 to 213 cGy. The sensitivity did not significantly change with the variation of SSD (±1%), field size (±1%), frame rate (±3%), or beam energy (±5%). The detector angular dependence was within ±5% over 360° and the dose recorded by the MOSkin detector in different depths of a solid water phantom was in good agreement with the Markus parallel plate ionization chamber to within ±3%. Conclusions: The MOSkin detector proved to be reliable when exposed to different field sizes, SSDs, depths in solid water, dose rates, frame rates, and radiation incident angles within a clinical x-ray beam. The MOSkin detector with water equivalent depth equal to 0.07 mm is a suitable detector for in vivo skin dosimetry during interventional radiology procedures.

  12. Assessment of radiation dose awareness among pediatricians

    International Nuclear Information System (INIS)

    Thomas, Karen E.; Parnell-Parmley, June E.; Charkot, Ellen; BenDavid, Guila; Krajewski, Connie; Haidar, Salwa; Moineddin, Rahim

    2006-01-01

    There is increasing awareness among pediatric radiologists of the potential risks associated with ionizing radiation in medical imaging. However, it is not known whether there has been a corresponding increase in awareness among pediatricians. To establish the level of awareness among pediatricians of the recent publicity on radiation risks in children, knowledge of the relative doses of radiological investigations, current practice regarding parent/patient discussions, and the sources of educational input. Multiple-choice survey. Of 220 respondents, 105 (48%) were aware of the 2001 American Journal of Roentgenology articles on pediatric CT and radiation, though only 6% were correct in their estimate of the quoted lifetime excess cancer risk associated with radiation doses equivalent to pediatric CT. A sustained or transient increase in parent questioning regarding radiation doses had been noticed by 31%. When estimating the effective doses of various pediatric radiological investigations in chest radiograph (CXR) equivalents, 87% of all responses (and 94% of CT estimates) were underestimates. Only 15% of respondents were familiar with the ALARA principle. Only 14% of pediatricians recalled any relevant formal teaching during their specialty training. The survey response rate was 40%. Awareness of radiation protection issues among pediatricians is generally low, with widespread underestimation of relative doses and risks. (orig.)

  13. Role of the Federal Radiological Monitoring and Assessment Center (FRMAC) following a radiological accident

    International Nuclear Information System (INIS)

    Doyle, J.F. III.

    1986-01-01

    The Federal Radiological Emergency Response Plan (FRERP) calls for the Department of Energy to establish a Federal Radiological Monitoring and Assessment Center (FRMAC) immediately following a major radiological accident to coordinate all federal off-site monitoring efforts in support of the State and the Cognizant Federal Agency (CFA) for the facility or material involved in the accident. Some accidents are potentailly very complex and may require hundreds of radiation specialists to ensure immediate protection of the public and workers in the area, and to identify priorities for the Environmental Protection Agency (EPA) long-term efforts once the immediate protective actions have been carried out. The FRMAC provides a working environment with today's high technology tools (i.e., communication, computers, management procedures, etc.) to assure that the State and CFA decision makers have the best possible information in a timely manner on which to act. The FRMAC planners also recognize an underlying responsibility to continuously document such operations in order to provide the State, the CFA, and the EPA the technical information they will require for long term assessments. In addition, it is fully recognized that information collected and actions taken by the FRMAC will be subjected to the same scrutiny as other parts of the accident and the overall response

  14. Estimation of patient radiation doses during radiologic examinations in the Republic of Haiti

    International Nuclear Information System (INIS)

    Massillon, J.G.; Borras, C.

    2001-01-01

    The International Commission on Radiological Protection and the international organizations that co-sponsored the International Basic Safety Standards for the Protection against Ionization Radiation and for the Safety of Radiation Sources (BSS) - among them PAHO and WHO - recommended the use of investigation levels to provide guidance for medical exposures. In this work, entrance surface doses for several common diagnostic radiology procedure have been determined from exposure rate measurements and patient technique factors in seven 'World Health Imaging System - Radiography' (WHIS-RAD) units, installed in public health services facilities of the Republic of Haiti. The results show the entrance surface doses below the guidance levels published in the BSS. Concomitant image quality measurements performed, however, indicate serious artifacts in the film processing, calling for the need of additional training of the technologists. (author)

  15. Irrigation in dose assessments models

    Energy Technology Data Exchange (ETDEWEB)

    Bergstroem, Ulla; Barkefors, Catarina [Studsvik RadWaste AB, Nykoeping (Sweden)

    2004-05-01

    SKB has carried out several safety analyses for repositories for radioactive waste, one of which was SR 97, a multi-site study concerned with a future deep bedrock repository for high-level waste. In case of future releases due to unforeseen failure of the protective multiple barrier system, radionuclides may be transported with groundwater and may reach the biosphere. Assessments of doses have to be carried out with a long-term perspective. Specific models are therefore employed to estimate consequences to man. It has been determined that the main pathway for nuclides from groundwater or surface water to soil is via irrigation. Irrigation may cause contamination of crops directly by e.g. interception or rain-splash, and indirectly via root-uptake from contaminated soil. The exposed people are in many safety assessments assumed to be self-sufficient, i.e. their food is produced locally where the concentration of radionuclides may be the highest. Irrigation therefore plays an important role when estimating consequences. The present study is therefore concerned with a more extensive analysis of the role of irrigation for possible future doses to people living in the area surrounding a repository. Current irrigation practices in Sweden are summarised, showing that vegetables and potatoes are the most common crops for irrigation. In general, however, irrigation is not so common in Sweden. The irrigation model used in the latest assessments is described. A sensitivity analysis is performed showing that, as expected, interception of irrigation water and retention on vegetation surfaces are important parameters. The parameters used to describe this are discussed. A summary is also given how irrigation is proposed to be handled in the international BIOMASS (BIOsphere Modelling and ASSessment) project and in models like TAME and BIOTRAC. Similarities and differences are pointed out. Some numerical results are presented showing that surface contamination in general gives the

  16. Irrigation in dose assessments models

    International Nuclear Information System (INIS)

    Bergstroem, Ulla; Barkefors, Catarina

    2004-05-01

    SKB has carried out several safety analyses for repositories for radioactive waste, one of which was SR 97, a multi-site study concerned with a future deep bedrock repository for high-level waste. In case of future releases due to unforeseen failure of the protective multiple barrier system, radionuclides may be transported with groundwater and may reach the biosphere. Assessments of doses have to be carried out with a long-term perspective. Specific models are therefore employed to estimate consequences to man. It has been determined that the main pathway for nuclides from groundwater or surface water to soil is via irrigation. Irrigation may cause contamination of crops directly by e.g. interception or rain-splash, and indirectly via root-uptake from contaminated soil. The exposed people are in many safety assessments assumed to be self-sufficient, i.e. their food is produced locally where the concentration of radionuclides may be the highest. Irrigation therefore plays an important role when estimating consequences. The present study is therefore concerned with a more extensive analysis of the role of irrigation for possible future doses to people living in the area surrounding a repository. Current irrigation practices in Sweden are summarised, showing that vegetables and potatoes are the most common crops for irrigation. In general, however, irrigation is not so common in Sweden. The irrigation model used in the latest assessments is described. A sensitivity analysis is performed showing that, as expected, interception of irrigation water and retention on vegetation surfaces are important parameters. The parameters used to describe this are discussed. A summary is also given how irrigation is proposed to be handled in the international BIOMASS (BIOsphere Modelling and ASSessment) project and in models like TAME and BIOTRAC. Similarities and differences are pointed out. Some numerical results are presented showing that surface contamination in general gives the

  17. Estimation of staff lens doses during interventional procedures. Comparing cardiology, neuroradiology and interventional radiology

    International Nuclear Information System (INIS)

    Vano, E.; Sanchez, R.M.; Fernandez, J.M.

    2015-01-01

    The purpose of this article is to estimate lens doses using over apron active personal dosemeters in interventional catheterisation laboratories (cardiology IC, neuroradiology IN and radiology IR) and to investigate correlations between occupational lens doses and patient doses. Active electronic personal dosemeters placed over the lead apron were used on a sample of 204 IC procedures, 274 IN and 220 IR (all performed at the same university hospital). Patient dose values (kerma area product) were also recorded to evaluate correlations with occupational doses. Operators used the ceiling-suspended screen in most cases. The median and third quartile values of equivalent dose Hp(10) per procedure measured over the apron for IC, IN and IR resulted, respectively, in 21/67, 19/44 and 24/54 μSv. Patient dose values (median/third quartile) were 75/128, 83/176 and 61/159 Gy cm 2 , respectively. The median ratios for dosemeters worn over the apron by operators ( protected by the ceiling-suspended screen) and patient doses were 0.36; 0.21 and 0.46 μSv Gy -1 cm -2 , respectively. With the conservative approach used (lens doses estimated from the over apron chest dosemeter) we came to the conclusion that more than 800 procedures y -1 and per operator were necessary to reach the new lens dose limit for the three interventional specialties. (authors)

  18. Assessment of natural radioactivity and associated radiological risks from tiles used in Kajang, Malaysia

    Science.gov (United States)

    Abdullahi, S.; Ismail, A. F.; Samat, S. B.; Yasir, M. S.

    2018-04-01

    The activity concentration and radiological risk of commonly used flooring materials (tiles) in Malaysia were studied. The natural radionuclide concentrations of 226Ra, 232Th and 40K were measured using high-purity germanium detector. The average concentration of 226Ra, 232Th and 40K in the samples were 65.75±1.1 Bq kg-1, 61.92±1.43 Bq kg-1 and 617.77±6.72 Bq kg-1 respectively. The mean concentration of radium equivalent activity, absorbed dose rate, external and internal hazard indices and annual effective dose equivalent were 195.21±2.88 Bq kg-1, 92.75±1.27 nGy h-1, 0.53±0.01, 0.7±0.01 and 0.44±0.0 mSv y-1 respectively. The aim was to assess the possible radiological risks attributed from the tile materials. Even though, the activity concentrations were higher than worldwide average values, but none of the radiological impact parameters exceeded the maximum recommended values. Hence, it was concluded that, contribution of tiles to radiation exposure is negligible and therefore, radiologically safe to use as building materials.

  19. Preliminary radiological assessments of low-level waste repositories

    International Nuclear Information System (INIS)

    Nancarrow, D.J.; Sumerling, T.J.; Ashton, J.

    1988-06-01

    Preliminary assessments of the post-closure radiological impact from the disposal of low-level radioactive wastes in shallow engineered facilities at four sites are presented. This provides a framework to practice and refine a methodology that could be used, on behalf of the Department, for independent assessment of any similar proposal from Nirex. Information and methodological improvements that would be required are identified. (author)

  20. Modeling and Analysis on Radiological Safety Assessment of Low- and Intermediate Level Radioactive Waste Repository

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Youn Myoung; Jung, Jong Tae; Kang, Chul Hyung (and others)

    2008-04-15

    Modeling study and analysis for technical support for the safety and performance assessment of the low- and intermediate level (LILW) repository partially needed for radiological environmental impact reporting which is essential for the licenses for construction and operation of LILW has been fulfilled. Throughout this study such essential area for technical support for safety and performance assessment of the LILW repository and its licensing as gas generation and migration in and around the repository, risk analysis and environmental impact during transportation of LILW, biosphere modeling and assessment for the flux-to-dose conversion factors for human exposure as well as regional and global groundwater modeling and analysis has been carried out.

  1. Modeling and Analysis on Radiological Safety Assessment of Low- and Intermediate Level Radioactive Waste Repository

    International Nuclear Information System (INIS)

    Lee, Youn Myoung; Jung, Jong Tae; Kang, Chul Hyung

    2008-04-01

    Modeling study and analysis for technical support for the safety and performance assessment of the low- and intermediate level (LILW) repository partially needed for radiological environmental impact reporting which is essential for the licenses for construction and operation of LILW has been fulfilled. Throughout this study such essential area for technical support for safety and performance assessment of the LILW repository and its licensing as gas generation and migration in and around the repository, risk analysis and environmental impact during transportation of LILW, biosphere modeling and assessment for the flux-to-dose conversion factors for human exposure as well as regional and global groundwater modeling and analysis has been carried out

  2. Radiological Assessments and Enhanced Natural Radioactivity

    International Nuclear Information System (INIS)

    Zeevaert, T.; Vanmaercke, H.; Paridaens, K.

    2001-01-01

    The objectives of the research in the field of the environmental impact assessment models performed the Belgian Nuclear Research Centre SCK-CEN are (1) to elaborate and to improve methods and guidelines for the evaluation of restoration options for contaminated sites; (2) to develop, test and improve biosphere models for the performance assessment of radioactive waste disposal in near-surface or geological repositories; (3) to asses the impact of releases from nuclear or industrial installations; (4) to apply new techniques for retrospective radon measurements and to assess radon decay product exposure by combining these techniques; and (5) to increase capabilities in mapping and surveying sites possibly or likely contaminated with enhanced levels of natural radiation. Main achievements in these areas for 2000 are summarised

  3. Technology Assessment and Roadmap for the Emergency Radiation Dose Assessment Program

    Energy Technology Data Exchange (ETDEWEB)

    Turteltaub, K W; Hartman-Siantar, C; Easterly, C; Blakely, W

    2005-10-03

    A Joint Interagency Working Group (JIWG) under the auspices of the Department of Homeland Security Office of Research and Development conducted a technology assessment of emergency radiological dose assessment capabilities as part of the overall need for rapid emergency medical response in the event of a radiological terrorist event in the United States. The goal of the evaluation is to identify gaps and recommend general research and development needs to better prepare the Country for mitigating the effects of such an event. Given the capabilities and roles for responding to a radiological event extend across many agencies, a consensus of gaps and suggested development plans was a major goal of this evaluation and road-mapping effort. The working group consisted of experts representing the Departments of Homeland Security, Health and Human Services (Centers for Disease Control and the National Institutes of Health), Food and Drug Administration, Department of Defense and the Department of Energy's National Laboratories (see appendix A for participants). The specific goals of this Technology Assessment and Roadmap were to: (1) Describe the general context for deployment of emergency radiation dose assessment tools following terrorist use of a radiological or nuclear device; (2) Assess current and emerging dose assessment technologies; and (3) Put forward a consensus high-level technology roadmap for interagency research and development in this area. This report provides a summary of the consensus of needs, gaps and recommendations for a research program in the area of radiation dosimetry for early response, followed by a summary of the technologies available and on the near-term horizon. We then present a roadmap for a research program to bring present and emerging near-term technologies to bear on the gaps in radiation dose assessment and triage. Finally we present detailed supporting discussion on the nature of the threats we considered, the status of

  4. Technology Assessment and Roadmap for the Emergency Radiation Dose Assessment Program

    International Nuclear Information System (INIS)

    Turteltaub, K W; Hartman-Siantar, C; Easterly, C; Blakely, W

    2005-01-01

    A Joint Interagency Working Group (JIWG) under the auspices of the Department of Homeland Security Office of Research and Development conducted a technology assessment of emergency radiological dose assessment capabilities as part of the overall need for rapid emergency medical response in the event of a radiological terrorist event in the United States. The goal of the evaluation is to identify gaps and recommend general research and development needs to better prepare the Country for mitigating the effects of such an event. Given the capabilities and roles for responding to a radiological event extend across many agencies, a consensus of gaps and suggested development plans was a major goal of this evaluation and road-mapping effort. The working group consisted of experts representing the Departments of Homeland Security, Health and Human Services (Centers for Disease Control and the National Institutes of Health), Food and Drug Administration, Department of Defense and the Department of Energy's National Laboratories (see appendix A for participants). The specific goals of this Technology Assessment and Roadmap were to: (1) Describe the general context for deployment of emergency radiation dose assessment tools following terrorist use of a radiological or nuclear device; (2) Assess current and emerging dose assessment technologies; and (3) Put forward a consensus high-level technology roadmap for interagency research and development in this area. This report provides a summary of the consensus of needs, gaps and recommendations for a research program in the area of radiation dosimetry for early response, followed by a summary of the technologies available and on the near-term horizon. We then present a roadmap for a research program to bring present and emerging near-term technologies to bear on the gaps in radiation dose assessment and triage. Finally we present detailed supporting discussion on the nature of the threats we considered, the status of technology

  5. Online dose rate monitoring: Better information by using the IRMA concept (Integral Radiological Multidetector Arrays)

    International Nuclear Information System (INIS)

    Genrich, V.

    1989-01-01

    A new GM detector system has been developed for online environmental monitoring. The approach is unorthodox, but simple: A) Take a set of radiological probes and feed all their information to an 'intelligent' front-end. B) Elaborate some algorithms, so that the system will give out just one gamma dose rate (running over more than nine decades). C) If necessary, associate some additional sensors, and the system will exhibit better discriminating qualities for the detection of artificial nuclides in the environment. (orig.)

  6. Thyroid Radiation Dose to Patients from Diagnostic Radiology Procedures over Eight Decades: 1930-2010.

    Science.gov (United States)

    Chang, Lienard A; Miller, Donald L; Lee, Choonsik; Melo, Dunstana R; Villoing, Daphnée; Drozdovitch, Vladimir; Thierry-Chef, Isabelle; Winters, Sarah J; Labrake, Michael; Myers, Charles F; Lim, Hyeyeun; Kitahara, Cari M; Linet, Martha S; Simon, Steven L

    2017-12-01

    This study summarizes and compares estimates of radiation absorbed dose to the thyroid gland for typical patients who underwent diagnostic radiology examinations in the years from 1930 to 2010. The authors estimated the thyroid dose for common examinations, including radiography, mammography, dental radiography, fluoroscopy, nuclear medicine, and computed tomography (CT). For the most part, a clear downward trend in thyroid dose over time for each procedure was observed. Historically, the highest thyroid doses came from the nuclear medicine thyroid scans in the 1960s (630 mGy), full-mouth series dental radiography (390 mGy) in the early years of the use of x rays in dentistry (1930s), and the barium swallow (esophagram) fluoroscopic exam also in the 1930s (140 mGy). Thyroid uptake nuclear medicine examinations and pancreatic scans also gave relatively high doses to the thyroid (64 mGy and 21 mGy, respectively, in the 1960s). In the 21st century, the highest thyroid doses still result from nuclear medicine thyroid scans (130 mGy), but high thyroid doses are also associated with chest/abdomen/pelvis CT scans (18 and 19 mGy for males and females, respectively). Thyroid doses from CT scans did not exhibit the same downward trend as observed for other examinations. The largest thyroid doses from conventional radiography came from cervical spine and skull examinations. Thyroid doses from mammography (which began in the 1960s) were generally a fraction of 1 mGy. The highest average doses to the thyroid from mammography were about 0.42 mGy, with modestly larger doses associated with imaging of breasts with large compressed thicknesses. Thyroid doses from dental radiographic procedures have decreased markedly throughout the decades, from an average of 390 mGy for a full-mouth series in the 1930s to an average of 0.31 mGy today. Upper GI series fluoroscopy examinations resulted in up to two orders of magnitude lower thyroid doses than the barium swallow. There are

  7. External dose assessment in the Ukraine following the Chernobyl accident

    Science.gov (United States)

    Frazier, Remi Jordan Lesartre

    While the physiological effects of radiation exposure have been well characterized in general, it remains unclear what the relationship is between large-scale radiological events and psychosocial behavior outcomes in individuals or populations. To investigate this, the National Science Foundation funded a research project in 2008 at the University of Colorado in collaboration with Colorado State University to expand the knowledge of complex interactions between radiation exposure, perception of risk, and psychosocial behavior outcomes by modeling outcomes for a representative sample of the population of the Ukraine which had been exposed to radiocontaminant materials released by the reactor accident at Chernobyl on 26 April 1986. In service of this project, a methodology (based substantially on previously published models specific to the Chernobyl disaster and the Ukrainian population) was developed for daily cumulative effective external dose and dose rate assessment for individuals in the Ukraine for as a result of the Chernobyl disaster. A software platform was designed and produced to estimate effective external dose and dose rate for individuals based on their age, occupation, and location of residence on each day between 26 April 1986 and 31 December 2009. A methodology was developed to transform published 137Cs soil deposition contour maps from the Comprehensive Atlas of Caesium Deposition on Europe after the Chernobyl Accident into a geospatial database to access these data as a radiological source term. Cumulative effective external dose and dose rate were computed for each individual in a 703-member cohort of Ukrainians randomly selected to be representative of the population of the country as a whole. Error was estimated for the resulting individual dose and dose rate values with Monte Carlo simulations. Distributions of input parameters for the dose assessment methodology were compared to computed dose and dose rate estimates to determine which

  8. Models and parameters for environmental radiological assessments

    International Nuclear Information System (INIS)

    Miller, C.W.

    1984-01-01

    This book presents a unified compilation of models and parameters appropriate for assessing the impact of radioactive discharges to the environment. Models examined include those developed for the prediction of atmospheric and hydrologic transport and deposition, for terrestrial and aquatic food-chain bioaccumulation, and for internal and external dosimetry. Chapters have been entered separately into the data base

  9. Models and parameters for environmental radiological assessments

    Energy Technology Data Exchange (ETDEWEB)

    Miller, C W [ed.

    1984-01-01

    This book presents a unified compilation of models and parameters appropriate for assessing the impact of radioactive discharges to the environment. Models examined include those developed for the prediction of atmospheric and hydrologic transport and deposition, for terrestrial and aquatic food-chain bioaccumulation, and for internal and external dosimetry. Chapters have been entered separately into the data base. (ACR)

  10. Quality control of diagnostic radiology to reduce absorbed dose of patients in Iran

    International Nuclear Information System (INIS)

    Aghahadi, Bahman.

    1996-01-01

    In order to reduce absorbed dose, to increase the image quality and to reduce the numbers of rejected films various quality control parameters were applied to X ray machines. These parameter are Kilo Volt peak, Milli Ampere, Exposure Time Focal Film Distance, Inherent Filters, Additional Filters Half Value Layer, Processor Condition, Cassettes. To evaluate and to apply these parameters in diagnostic radiological centers, ten hospitals were selected and a total number of 12 X ray machines were kept under quality control program. Considering different kinds of diagnostic radiology examination and to compare the dose before and after implementation of a quality control program, two kinds of examinations include in chest and abdomen examinations were considered. For each X ray machine, ten patients and for all selected centers, 120 patients were selected for chest examination and 120 patients for abdomen examinations; before and after implementation of quality control program, a total of 480 patients were selected randomly to be controlled. Base on different examinations carried out, it was concluded that both exposure conditions and general situations in radiological centers were not acceptable. The dosimetry results show that the average ski dose for chest and abdomen examinations were 0.28 m Gy and 4.23 Gy respectively. Before implementation of quality control step to reduce the surface skin dose, quality control parameters were applied and the exposure conditions were imposed. On average the absorbed doses for chest and abdomen examination were decreased to 79% and 61% respectively after the implementation of the program. From dose reduction point of view, the results of a part of this project which made by co-operation of International Atomic Energy Agency showed that Iran acquired the first grade for chest examination and second grade for abdomen examination. Base on the results obtained, the number of patients under chest and abdomen examination were 4041588 and

  11. Determining and managing fetal radiation dose from diagnostic radiology procedures in Turkey

    International Nuclear Information System (INIS)

    Ozbayrak, Mustafa; Cavdar, Iffet; Seven, Mehmet; Uslu, Lebriz; Yeyin, Nami; Tanyildizi, Handan; Abuqbeitah, Mohammad; Acikgoz, A. Serdar; Tuten, Abdullah; Demir, Mustafa

    2015-01-01

    We intended to calculate approximate fetal doses in pregnant women who underwent diagnostic radiology procedures and to evaluate the safety of their pregnancies. We contacted hospitals in different cities in Turkey where requests for fetal dose calculation are usually sent. Fetal radiation exposure was calculated for 304 cases in 218 pregnant women with gestational ages ranging from 5 days to 19 weeks, 2 days. FetDose software (ver. 4.0) was used in fetal dose calculations for radiographic and computed tomography (CT) procedures. The body was divided into three zones according to distance from the fetus. The first zone consisted of the head area, the lower extremities below the knee, and the upper extremities; the second consisted of the cervicothoracic region and upper thighs; and the third consisted of the abdominopelvic area. Fetal doses from radiologic procedures between zones were compared using the Kruskal-Wallis test and a Bonferroni-corrected Mann-Whitney U-test. The average fetal doses from radiography and CT in the first zone were 0.05 ± 0.01 mGy and 0.81 ± 0.04 mGy, respectively; 0.21 ± 0.05 mGy and 1.77 ± 0.22 mGy, respectively, in the second zone; and 6.42 ± 0.82 mGy and 22.94 ± 1.28 mGy, respectively, in the third zone (p < 0.001). Our results showed that fetal radiation exposures in our group of pregnant women did not reach the level (50 mGy) that is known to increase risk for congenital anomalies. Fetal radiation exposure in the diagnostic radiology procedures in our study did not reach risk levels that might have indicated abortion

  12. Determining and managing fetal radiation dose from diagnostic radiology procedures in Turkey

    Energy Technology Data Exchange (ETDEWEB)

    Ozbayrak, Mustafa; Cavdar, Iffet; Seven, Mehmet; Uslu, Lebriz; Yeyin, Nami; Tanyildizi, Handan; Abuqbeitah, Mohammad; Acikgoz, A. Serdar; Tuten, Abdullah; Demir, Mustafa [Istanbul University, Istanbul (Turkmenistan)

    2015-12-15

    We intended to calculate approximate fetal doses in pregnant women who underwent diagnostic radiology procedures and to evaluate the safety of their pregnancies. We contacted hospitals in different cities in Turkey where requests for fetal dose calculation are usually sent. Fetal radiation exposure was calculated for 304 cases in 218 pregnant women with gestational ages ranging from 5 days to 19 weeks, 2 days. FetDose software (ver. 4.0) was used in fetal dose calculations for radiographic and computed tomography (CT) procedures. The body was divided into three zones according to distance from the fetus. The first zone consisted of the head area, the lower extremities below the knee, and the upper extremities; the second consisted of the cervicothoracic region and upper thighs; and the third consisted of the abdominopelvic area. Fetal doses from radiologic procedures between zones were compared using the Kruskal-Wallis test and a Bonferroni-corrected Mann-Whitney U-test. The average fetal doses from radiography and CT in the first zone were 0.05 ± 0.01 mGy and 0.81 ± 0.04 mGy, respectively; 0.21 ± 0.05 mGy and 1.77 ± 0.22 mGy, respectively, in the second zone; and 6.42 ± 0.82 mGy and 22.94 ± 1.28 mGy, respectively, in the third zone (p < 0.001). Our results showed that fetal radiation exposures in our group of pregnant women did not reach the level (50 mGy) that is known to increase risk for congenital anomalies. Fetal radiation exposure in the diagnostic radiology procedures in our study did not reach risk levels that might have indicated abortion.

  13. Pathway analysis concepts for radiological impact assessment

    International Nuclear Information System (INIS)

    Moroney, J.R.

    1992-06-01

    The concepts underlying exposure pathways analysis are outlined with reference to the features of the two broad types of radionuclide transport models now in use - dynamic and steady-state - and the methods for constructing and developing them. By way of illustration, representative radiation doses are estimated for the four main exposure pathways likely to be involved in the land application of effluent water from Retention Pond 2 of Ranger Uranium Mines. These include: external irradiation by 226 Ra and natural uranium (Un at) in soil, ingestion of 226 Ra and Un at in food, inhalation of 222 Rn daughter products from 226 Rn in soil, and inhalation of 226 Ra and Un at in airborne dust resuspended from soil. Consideration has been given to local residents pursuing a traditional lifestyle on conclusion of the land application program. Because of the possible importance of the contribution from resuspended dust, currently available data are explored in refining the methodology for the pathway and developing a more appropriate model for it. 37 refs., 9 tabs., 6 figs

  14. SU-D-209-03: Radiation Dose Reduction Using Real-Time Image Processing in Interventional Radiology

    Energy Technology Data Exchange (ETDEWEB)

    Kanal, K; Moirano, J; Zamora, D; Stewart, B [University Washington, Seattle, WA (United States)

    2016-06-15

    Purpose: To characterize changes in radiation dose after introducing a new real-time image processing technology in interventional radiology systems. Methods: Interventional radiology (IR) procedures are increasingly complex, at times requiring substantial time and radiation dose. The risk of inducing tissue reactions as well as long-term stochastic effects such as radiation-induced cancer is not trivial. To reduce this risk, IR systems are increasingly equipped with dose reduction technologies.Recently, ClarityIQ (Philips Healthcare) technology was installed in our existing neuroradiology IR (NIR) and vascular IR (VIR) suites respectively. ClarityIQ includes real-time image processing that reduces noise/artifacts, enhances images, and sharpens edges while also reducing radiation dose rates. We reviewed 412 NIR (175 pre- and 237 post-ClarityIQ) procedures and 329 VIR (156 preand 173 post-ClarityIQ) procedures performed at our institution pre- and post-ClarityIQ implementation. NIR procedures were primarily classified as interventional or diagnostic. VIR procedures included drain port, drain placement, tube change, mesenteric, and implanted venous procedures. Air Kerma (AK in units of mGy) was documented for all the cases using a commercial radiation exposure management system. Results: When considering all NIR procedures, median AK decreased from 1194 mGy to 561 mGy. When considering all VIR procedures, median AK decreased from 49 to 14 mGy. Both NIR and VIR exhibited a decrease in AK exceeding 50% after ClarityIQ implementation, a statistically significant (p<0.05) difference. Of the 5 most common VIR procedures, all median AK values decreased, but significance (p<0.05) was only reached in venous access (N=53), angio mesenteric (N=41), and drain placement procedures (N=31). Conclusion: ClarityIQ can reduce dose significantly for both NIR and VIR procedures. Image quality was not assessed in conjunction with the dose reduction.

  15. Exposure dose assessment using bioassay

    International Nuclear Information System (INIS)

    Suga, Shinichi

    1994-01-01

    Bioassay involves following steps: sampling, pre-treatment, chemical separation and counting of radioactivity. As bioassay samples, urines are usually used, although faecal analysis may be required in some occasions for example to assess intake of non-transferable radioactive materials. Nasal smear is a useful indicator of an inhalation case. Exhalation air is used to estimate the intake of tritiated water. Sample pre-treatment includes evaporation for concentration, wet ashing, dry ashing and co-precipitation. After adding small amount of nitric acid, the sample can be concentrated by 1/10 of initial volume, which may be used to identify γ-emitters. As the pre-treatment of urine, wet ashing is used for example for analysis of Pu, and co-precipitation is used for example for analysis of Sr. Dry ashing by electric furnace is usually adopted for faecal samples. Methods of chemical separation depend on the radionuclide(s) to be analysed. The detection limit depends also on radionuclide, and for example typical detection limits are 0.4Bq / l (volume of urine sample) for 89 Sr or 90 Sr, and 0.01 Bq / l with urine and 0.01 Bq per sample with faeces for 238 Pu, 239 Pu or 241 Am. Simpler methods can be used for some radionuclides: For example, radioactivity concentration of tritium can be determined by liquid scintillation counting of urine or condensed water from exhaled air, and natural uranium in urine can be quantified by using fluorometric method. In some circumstances, gross-α or gross-β analyses are useful for quick estimation. To estimate intakes by inhalation or by ingestion from bioassay results and to assess the committed dose equivalent, commonly available bases are the relevant publications by the ICRP and domestic guides and manuals that conform to the radiation protection regulations. (author)

  16. Radiation dose to children in diagnostic radiology. Measurements and methods for clinical optimisation studies

    International Nuclear Information System (INIS)

    Almen, A.J.

    1995-09-01

    A method for estimating mean absorbed dose to different organs and tissues was developed for paediatric patients undergoing X-ray investigations. The absorbed dose distribution in water was measured for the specific X-ray beam used. Clinical images were studied to determine X-ray beam positions and field sizes. Size and position of organs in the patient were estimated using ORNL phantoms and complementary clinical information. Conversion factors between the mean absorbed dose to various organs and entrance surface dose for five different body sizes were calculated. Direct measurements on patients estimating entrance surface dose and energy imparted for common X-ray investigations were performed. The examination technique for a number of paediatric X-ray investigations used in 19 Swedish hospitals was studied. For a simulated pelvis investigation of a 1-year old child the entrance surface dose was measured and image quality was estimated using a contrast-detail phantom. Mean absorbed doses to organs and tissues in urography, lung, pelvis, thoracic spine, lumbar spine and scoliosis investigations was calculated. Calculations of effective dose were supplemented with risk calculations for special organs e g the female breast. The work shows that the examination technique in paediatric radiology is not yet optimised, and that the non-optimised procedures contribute to a considerable variation in radiation dose. In order to optimise paediatric radiology there is a need for more standardised methods in patient dosimetry. It is especially important to relate measured quantities to the size of the patient, using e g the patient weight and length. 91 refs, 17 figs, 8 tabs

  17. Radiation dose to children in diagnostic radiology. Measurements and methods for clinical optimisation studies

    Energy Technology Data Exchange (ETDEWEB)

    Almen, A J

    1995-09-01

    A method for estimating mean absorbed dose to different organs and tissues was developed for paediatric patients undergoing X-ray investigations. The absorbed dose distribution in water was measured for the specific X-ray beam used. Clinical images were studied to determine X-ray beam positions and field sizes. Size and position of organs in the patient were estimated using ORNL phantoms and complementary clinical information. Conversion factors between the mean absorbed dose to various organs and entrance surface dose for five different body sizes were calculated. Direct measurements on patients estimating entrance surface dose and energy imparted for common X-ray investigations were performed. The examination technique for a number of paediatric X-ray investigations used in 19 Swedish hospitals was studied. For a simulated pelvis investigation of a 1-year old child the entrance surface dose was measured and image quality was estimated using a contrast-detail phantom. Mean absorbed doses to organs and tissues in urography, lung, pelvis, thoracic spine, lumbar spine and scoliosis investigations was calculated. Calculations of effective dose were supplemented with risk calculations for special organs e g the female breast. The work shows that the examination technique in paediatric radiology is not yet optimised, and that the non-optimised procedures contribute to a considerable variation in radiation dose. In order to optimise paediatric radiology there is a need for more standardised methods in patient dosimetry. It is especially important to relate measured quantities to the size of the patient, using e g the patient weight and length. 91 refs, 17 figs, 8 tabs.

  18. Study of the dose rate measured by the radiological surveillance network of the Basque country

    International Nuclear Information System (INIS)

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

    2006-01-01

    Full text of publication follows: The radiological Surveillance Network of the Basque Country, which is constituted by three stations located in Bilbao, Vitoria and San Sebastian, measures and records the dose date every 10 minutes. Some environmental parameters affect the behaviour of the dose rate. One of most important meteorological parameters is rain. So, it has been necessary to study separately the behaviour of dose rate in the absence of rain, defining that time as Dry Time, and the behaviour when it rains, designating that time as Wet Time. Previous studies have confirmed that dose rate values are fitted to normal distributions, and in those cases, Critical Limits can be calculated using Curie formulation. Every January, data recorded in previous year, two Critical Limits are obtained, one of them for dry time and other one for wet time, and both together define the Alarm Level for each radiological station. That Alarm Level is the reference value for dose rate. If some dose rate value is higher than the corresponding Alarm Level, the recorded values have to be studied in order to identify the origin or the cause of that value. In most cases, in which the dose rate is higher than the corresponding Alarm Level due to precipitation, occurs that when rain stops the dose rate value does not fall immediately to dry rime values, and then the Alarm Level which is now that for dry time is exceeded by the dose rate. So, those values can be considered a special group called Transition Area. The second part of the study tries to explain the cause and the behaviour of the values in the transition Area by means of the study of the behaviour of radon daughters in the atmosphere and their deposition onto the ground during rain intervals. To check the results several situations have been simulated using the Monte Carlo code MCNP-4C. (authors)

  19. Assessment of radiological technologist health condition by Todai health index

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ham Gyum [Ansan College, Ansan (Korea, Republic of); Kim, Wha Sun [College of Medicine, Hanyang Univ., Seoul (Korea, Republic of)

    2001-04-01

    The purpose of this study was to examine the general health status of radiological technologists by using Todai Health Index(THI) that has been employed as a standard health assessment tool for a specific group. The subjects in this study were 800 radiological technologists who were working in clinics, hospitals and university hospitals in and around Seoul and in some provincial cities. A survey was conducted directly or by mail in June and July, 2001. And the response rate was 68%. Using THI, the following findings were acquired: 1. By gender, both male and female radiological technologists complained about multiple subjective symptom(I) the most, And the women made more significant complaint of eight items including irregular life. 2. By age group, the radiological technologists whose age ranged from 20 to 24 got higher marks in most of the items, including multiple subjective symptom(I) and symptoms related to eyes and skin. 3. For career, those who had worked for a year or less or for one to five years got higher marks in most of the items. 4. Concerning marital status, the unmarried people complained about many items more, and the married people's symptom was more associated with live scale(L). 5. By the type of medical institution, the radiological technologists in the university hospitals got higher marks in two items including aggressiveness(F), but those in the clinics complained about the others more. 6. Regarding a place of service, there were little differences between the radiological technologists in basement and on the ground.

  20. Assessment of radiological technologist health condition by Todai health index

    International Nuclear Information System (INIS)

    Kim, Ham Gyum; Kim, Wha Sun

    2001-01-01

    The purpose of this study was to examine the general health status of radiological technologists by using Todai Health Index(THI) that has been employed as a standard health assessment tool for a specific group. The subjects in this study were 800 radiological technologists who were working in clinics, hospitals and university hospitals in and around Seoul and in some provincial cities. A survey was conducted directly or by mail in June and July, 2001. And the response rate was 68%. Using THI, the following findings were acquired: 1. By gender, both male and female radiological technologists complained about multiple subjective symptom(I) the most, And the women made more significant complaint of eight items including irregular life. 2. By age group, the radiological technologists whose age ranged from 20 to 24 got higher marks in most of the items, including multiple subjective symptom(I) and symptoms related to eyes and skin. 3. For career, those who had worked for a year or less or for one to five years got higher marks in most of the items. 4. Concerning marital status, the unmarried people complained about many items more, and the married people's symptom was more associated with live scale(L). 5. By the type of medical institution, the radiological technologists in the university hospitals got higher marks in two items including aggressiveness(F), but those in the clinics complained about the others more. 6. Regarding a place of service, there were little differences between the radiological technologists in basement and on the ground

  1. Chernobyl radiological data for accident consequence assessment

    International Nuclear Information System (INIS)

    Bottino, A.; Sacripanti, A.

    1989-01-01

    In this draft is presented the results of a first effort to summarize information related to the radionuclides behaviour in rural areas, in order to estimate pathway parameters to assess accident consequences. This topic encloses relevant aspects concerning contamination of rural environment, the most important being: 1) dry deposition velocities; 2) washout coefficient; 3) accumulation in lakes; 4) migration in soil; 5) winter conditions; 6) filtering effects of forests

  2. Chemical and radiological vulnerability assessment in urban areas

    Directory of Open Access Journals (Sweden)

    Stojanović Božidar

    2006-01-01

    Full Text Available Cities and towns are faced with various types of threat from the extraordinary events involving chemical and radiological materials as exemplified by major chemical accidents, radiological incidents, fires, explosions, traffic accidents, terrorist attacks, etc. On the other hand, many sensitive or vulnerable assets exist within cities, such as: settlements, infrastructures, hospitals, schools, churches, businesses, government, and others. Besides emergency planning, the land use planning also represents an important tool for prevention or reduction of damages on people and other assets due to unwanted events. This paper considers development of method for inclusion vulnerability assessment in land use planning with objective to assess and limit the consequences in cities of likely accidents involving hazardous materials. We made preliminary assessment of criticality and vulnerability of the assets within Belgrade city area in respect to chemical sites and transportation roads that can be exposed to chemical accidents, or terrorist attacks.

  3. Concerns in assessing radiological releases to a major estuary

    International Nuclear Information System (INIS)

    Foldesi, Leslie P.

    1989-01-01

    Full text: In the State of Virginia, the James River flows into the Chesapeake Bay and from the mouth of the James River to the fall line the river is under the influence of tidal forces. There are several centers of commerce along the river including an international port of call at the mouth of the James. Associated with the centers of commerce are potential sources of radioactive materials for being released to the river. Two hundred miles inland, the Babcock and Wilcox nuclear fuels processing plants are situated along-side the James River, which has been known to flood its banks quickly in the mountainous regions of Virginia. Storage tanks have been swept downstream from this facility in a previous flood. Fortunately, the tanks were not destroyed. Another source of a possible release is the Suny Nuclear Power Station located on the James River about fifty miles from the Chesapeake Bay. In the cities of Norfolk and Newport News, shipyards are fueling and defueling the Navy's nuclear powered fleet. In addition, many of the Navy's ships are carrying nuclear weapons. These activities may also result in an inadvertent release. In assessing the radiological release from any one of the previously mentioned activities, it is obvious that dilution of the material released into the river is a major factor in dose assessment, as well as the fact that the water is brackish and not suitable as a source of potable water. However, dilution in this case may not be the simple solution. We also have to remember that this estuary is under tidal effects, which means that the materials may not be going out to sea to be further diluted as quickly as we would like to think. It may be possible that the material will be carried up river as far as the fall line and deposited, or deposited along the river's banks. From Virginia's experience with the pesticide, Kepone, materials may be deposited along the estuary and enter the food chain thereby necessitating the limitation of taking

  4. Concerns in assessing radiological releases to a major estuary

    Energy Technology Data Exchange (ETDEWEB)

    Foldesi, Leslie P [Virginia Department of Health, Bureau of Radiological Health, Richmond, VA (United States)

    1989-09-01

    Full text: In the State of Virginia, the James River flows into the Chesapeake Bay and from the mouth of the James River to the fall line the river is under the influence of tidal forces. There are several centers of commerce along the river including an international port of call at the mouth of the James. Associated with the centers of commerce are potential sources of radioactive materials for being released to the river. Two hundred miles inland, the Babcock and Wilcox nuclear fuels processing plants are situated along-side the James River, which has been known to flood its banks quickly in the mountainous regions of Virginia. Storage tanks have been swept downstream from this facility in a previous flood. Fortunately, the tanks were not destroyed. Another source of a possible release is the Suny Nuclear Power Station located on the James River about fifty miles from the Chesapeake Bay. In the cities of Norfolk and Newport News, shipyards are fueling and defueling the Navy's nuclear powered fleet. In addition, many of the Navy's ships are carrying nuclear weapons. These activities may also result in an inadvertent release. In assessing the radiological release from any one of the previously mentioned activities, it is obvious that dilution of the material released into the river is a major factor in dose assessment, as well as the fact that the water is brackish and not suitable as a source of potable water. However, dilution in this case may not be the simple solution. We also have to remember that this estuary is under tidal effects, which means that the materials may not be going out to sea to be further diluted as quickly as we would like to think. It may be possible that the material will be carried up river as far as the fall line and deposited, or deposited along the river's banks. From Virginia's experience with the pesticide, Kepone, materials may be deposited along the estuary and enter the food chain thereby necessitating the limitation of taking

  5. Specification of carbon ion dose at the National Institute of Radiological Sciences (NIRS)

    International Nuclear Information System (INIS)

    Matsufuji, Naruhiro; Nakai, Tatsuaki; Kanematsu, Nobuyuki

    2007-01-01

    The clinical dose distributions of therapeutic carbon beams, currently used at National Institute of Radiological Sciences (NIRS) Heavy Ion Medical Accelerator in Chiba (HIMAC), are based on in-vitro Human Salivary Gland (HSG) cell survival response and clinical experience from fast neutron radiotherapy. Moderate radiosensitivity of HSG cells is expected to be a typical response of tumours to carbon beams. At first, the biological dose distribution is designed so as to cause a flat biological effect on HSG cells in the spread-out Bragg peak (SOBP) region. Then, the entire biological dose distribution is evenly raised in order to attain a RBE (relative biological effectiveness)=3.0 at a depth where dose-averaged LET (linear energy transfer) is 80 keV/μm. At that point, biological experiments have shown that carbon ions can be expected to have a biological effect identical to fast neutrons, which showed a clinical RBE of 3.0 for fast neutron radiotherapy at NIRS. The resulting clinical dose distribution in this approximation is not dependent on dose level, tumour type or fractionation scheme and thus reduces the unknown parameters in the analysis of the clinical results. The width SOBP and the clinical/physical dose at the center of SOBP specify the dose distribution. The clinical results analyzed in terms of tumor control probability (TCP) were found to show good agreement with the expected RBE value at higher TCP levels. The TCP analysis method was applied for the prospective dose estimation of hypofractionation. (author)

  6. Effective dose to patients in interventional vascular radiology in Malaga and Tenerife

    International Nuclear Information System (INIS)

    Ruiz Cruces, R.; Perez Martinez, M.; Diez de los Rios Delgado, A.; Hernandez Armas, J.; Garcia-Granados, J.; Diaz Romero, F.J.

    1997-01-01

    The objective of the research is to estimate the effective dose that patients receive during the procedure of interventional vascular radiology screening using a digital system. The effective dose is the best indicator of radiological risks. A plane ionization camera is used to estimate dose per surface area (Gy/square cm). By means of the method described in the NRPB R-262 report, projections were selected which adjust to the field irradiated in each of the procedures analysed. The product values of the dose surface and effective dose has been 75.7 Gy/cm 2 and 10.5 mSv for abdominal angiography; 29.0 Gy/cm 2 and 7.6 mSv for arteriographic diagnosis of the inferior members; 104.5 Gy/cm 2 and 23.6 mSv for gall drainage; 90.5 Gy/cm 2 and 21.5 mSv for varicoceles, and 39.5 Gy/cm 2 and 9.6 mSv for nephrostomas

  7. A pilot experience launching a national dose protocol for vascular and interventional radiology

    International Nuclear Information System (INIS)

    Vano, E.; Segarra, A.; Fernandez, J. M.; Ordiales, J. M.; Simon, R.; Gallego, J. J.; Del Cerro, J.; Casasola, E.; Verdu, J. F.; Ballester, T.; Sotil, J.; Aspiazu, A.; Garcia, M. A.; Moreno, F.; Carreras, F.; Canis, M.; Soler, M. M.; Palmero, J.; Ciudad, J.; Diaz, F.; Hernandez, J.; Gonzalez, M.; Rosales, P.

    2008-01-01

    The design of a national dose protocol for interventional radiology has been one of the tasks during the European SENTINEL Coordination Action. The present paper describes the pilot experience carried out in cooperation with the Spanish Society on Vascular and Interventional Radiology (SERVEI). A prospective sample of procedures was initially agreed. A common quality control of the X-ray systems was carried out, including calibration of the air kerma area product (KAP) meters. Occupational doses of the radiologists involved in the survey were also included in the survey. A total of 10 Spanish hospitals with interventional X-ray units were involved. Six hundred and sixty-four patient dose data were collected from 397 diagnostic and 267 therapeutic procedures. Occupational doses were evaluated in a sample of 635 values. The obtained KAP median/mean values (Gy.cm 2 ) for the gathered procedures were: biliary drainage (30.6/68.9), fistulography (4.5/9.8), lower limb arteriography (52.2/60.7), hepatic chemoembolisation (175.8/218.3), iliac stent (45.9/73.2) and renal arteriography (39.1/59.8). Occupational doses (mean monthly values, in mSv) were 1.9 (over apron); 0.3 (under apron) and 4.5 (on hands). With this National experience, a protocol was agreed among the SENTINEL partners to conduct future similar surveys in other European countries. (authors)

  8. Assessment of exposure dose to workers in virtual decommissioning environments

    International Nuclear Information System (INIS)

    Jeong, KwanSeong; Moon, JeiKwon; Choi, ByungSeon; Hyun, Dongjun; Lee, Jonghwan; Kim, Ikjune; Kim, GeunHo; Seo, JaeSeok

    2014-01-01

    This paper is intended to suggest the method analyze and assess the exposure dose to workers in virtual decommissioning environments. To simulate a lot of decommissioning scenarios, decommissioning environments were designed in virtual reality. To simulate and assess the exposure dose to workers, human model also was designed in virtual environments. These virtual decommissioning environments made it possible to real-time simulate and assess the exposure dose to workers. This work was to be able to simulate scenarios of decommissioning so that exposure dose to workers could be measured and assessed. To establish the plan of exposure dose to workers during decommissioning of nuclear facilities before decommissioning activities are accomplished, the method of simulation assessment was developed in virtual radiological environments. But this work was developed as a tool of simulation for single subject mode. Afterwards, the simulation environment for multi-subjects mode will be upgraded by simultaneous modules with networking environments. Then the much more practical method will be developed by changing number of workers and duration of time under any circumstances of decommissioning

  9. Assessment of exposure dose to workers in virtual decommissioning environments

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, KwanSeong; Moon, JeiKwon; Choi, ByungSeon; Hyun, Dongjun; Lee, Jonghwan; Kim, Ikjune; Kim, GeunHo; Seo, JaeSeok [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    This paper is intended to suggest the method analyze and assess the exposure dose to workers in virtual decommissioning environments. To simulate a lot of decommissioning scenarios, decommissioning environments were designed in virtual reality. To simulate and assess the exposure dose to workers, human model also was designed in virtual environments. These virtual decommissioning environments made it possible to real-time simulate and assess the exposure dose to workers. This work was to be able to simulate scenarios of decommissioning so that exposure dose to workers could be measured and assessed. To establish the plan of exposure dose to workers during decommissioning of nuclear facilities before decommissioning activities are accomplished, the method of simulation assessment was developed in virtual radiological environments. But this work was developed as a tool of simulation for single subject mode. Afterwards, the simulation environment for multi-subjects mode will be upgraded by simultaneous modules with networking environments. Then the much more practical method will be developed by changing number of workers and duration of time under any circumstances of decommissioning.

  10. Image and dose quality in selected studies of conventional radiology in designed hospitals

    International Nuclear Information System (INIS)

    Cardenas H, J.; Martinez G, A.; Machado T, A.; Mora M, R. de la; Pedroso, L.; Villa Z, R.; Sotolongo C, J.A.; Rodriguez S, R.M.; Martinez A, U.; Figueroa G, L.M.

    2006-01-01

    The medical exposures have a significant contribution to the received doses by the population. As they generally contribute to the patient's direct benefit during a lot of time has been paid smaller attention that to other exposure forms, in spite of existing potentialities of reducing dose to the patients as consequence of these applications. In such sense in the last years the scientific community and international organizations have defined requirements to contribute to that the doses to the patients are the minimum ones necessary to achieve its diagnostic objective. The work exposes the results obtained in the evaluation of the image quality and dose in studies of radiology of thorax posteroanterior and of lumbosacral column anteroposterior and lateral, carried out in 2 university hospitals of La Havana, as well as the contribution of this investigation to the establishment of guidance levels in our country. (Author)

  11. Direction Committee for the management of the post-accident phase of a nuclear accident or of a radiological event (CODIRPA). Work group 'Hypotheses'. Contextual data and hypotheses to perform predictive assessments of radiological and dose consequences at the beginning of a post-accidental transition phase. 2007-2009 work report

    International Nuclear Information System (INIS)

    2010-01-01

    This report first describes how to examine the various exposure ways of a person present on a contaminated territory and formulates hypotheses for the calculation of radioactive doses received by ingestion of contaminated food products, by external irradiation, or by involuntary inhalation of radioactive particles. It identifies factors which may influence the contamination of food products, and gives recommendations for the predictive calculation of their contamination during the first month following the accident. It indicates available methods for the predictive assessment of radioactive deposits at the beginning of the transition phase. It proposes an expertise method to assess the post-accident consequences

  12. Using SAFRAN Software to Assess Radiological Hazards from Dismantling of Tammuz-2 Reactor Core at Al-tuwaitha Nuclear Site

    Science.gov (United States)

    Abed Gatea, Mezher; Ahmed, Anwar A.; jundee kadhum, Saad; Ali, Hasan Mohammed; Hussein Muheisn, Abbas

    2018-05-01

    The Safety Assessment Framework (SAFRAN) software has implemented here for radiological safety analysis; to verify that the dose acceptance criteria and safety goals are met with a high degree of confidence for dismantling of Tammuz-2 reactor core at Al-tuwaitha nuclear site. The activities characterizing, dismantling and packaging were practiced to manage the generated radioactive waste. Dose to the worker was considered an endpoint-scenario while dose to the public has neglected due to that Tammuz-2 facility is located in a restricted zone and 30m berm surrounded Al-tuwaitha site. Safety assessment for dismantling worker endpoint-scenario based on maximum external dose at component position level in the reactor pool and internal dose via airborne activity while, for characterizing and packaging worker endpoints scenarios have been done via external dose only because no evidence for airborne radioactivity hazards outside the reactor pool. The in-situ measurements approved that reactor core components are radiologically activated by Co-60 radioisotope. SAFRAN results showed that the maximum received dose for workers are (1.85, 0.64 and 1.3mSv/y) for activities dismantling, characterizing and packaging of reactor core components respectively. Hence, the radiological hazards remain below the low level hazard and within the acceptable annual dose for workers in radiation field

  13. Proposed procedure and analysis of results to verify the indicator of the product dose-area in radiology equipment

    International Nuclear Information System (INIS)

    Garcia Marcos, R.; Gallego Franco, P.; Sierra Diaz, F.; Gonzalez Ruiz, C.; Rodriguez Checa, M.; Brasa Estevez, M.; Gomez Calvar, R.

    2013-01-01

    The aim of this work is to establish a procedure to verify the value of the product dose-area showing certain teams of Radiology, with an alternative to the use of external transmission cameras. (Author)

  14. A Probabilistic Assessment of the Chemical and Radiological Risks of Chronic Exposure to Uranium in Freshwater Ecosystems

    International Nuclear Information System (INIS)

    Mathews, T.; Beaugelin-Seiller, K.; Garnier-Laplace, J.; Gilbin, R.; Adam, Ch.; Della-Vedova, C.

    2009-01-01

    Uranium (U) presents a unique challenge for ecological risk assessments (ERA) because it induces both chemical and radiological toxicity, and the relative importance of these two toxicities differs among the various U source terms (i.e., natural, enriched, depleted). We present a method for the conversion between chemical concentrations (μgL -1 ) and radiological dose rates (μGyh -1 ) for a defined set of reference organisms, and apply this conversion method to previously derived chemical and radiological benchmarks to determine the extent to which these benchmarks ensure radiological and chemical protection, respectively, for U in freshwater ecosystems. Results show that the percentage of species radiologically protected by the chemical benchmark decreases with increasing degrees of U enrichment and with increasing periods of radioactive decay. In contrast, the freshwater ecosystem is almost never chemically protected by the radiological benchmark, regardless of the source term or decay period considered, confirming that the risks to the environment from uranium's chemical toxicity generally outweigh those of its radiological toxicity. These results are relevant to developing water quality criteria that protect freshwater ecosystems from the various risks associated with the nuclear applications of U exploitation, and highlight the need for (1) further research on the speciation, bioavailability, and toxicity of U-series radionuclides under different environmental conditions, and (2) the adoption of both chemical and radiological benchmarks for coherent ERAS to be conducted in U-contaminated freshwater ecosystems. (authors)

  15. Radiological interpretation 2020: Toward quantitative image assessment

    International Nuclear Information System (INIS)

    Boone, John M.

    2007-01-01

    The interpretation of medical images by radiologists is primarily and fundamentally a subjective activity, but there are a number of clinical applications such as tumor imaging where quantitative imaging (QI) metrics (such as tumor growth rate) would be valuable to the patient’s care. It is predicted that the subjective interpretive environment of the past will, over the next decade, evolve toward the increased use of quantitative metrics for evaluating patient health from images. The increasing sophistication and resolution of modern tomographic scanners promote the development of meaningful quantitative end points, determined from images which are in turn produced using well-controlled imaging protocols. For the QI environment to expand, medical physicists, physicians, other researchers and equipment vendors need to work collaboratively to develop the quantitative protocols for imaging, scanner calibrations, and robust analytical software that will lead to the routine inclusion of quantitative parameters in the diagnosis and therapeutic assessment of human health. Most importantly, quantitative metrics need to be developed which have genuine impact on patient diagnosis and welfare, and only then will QI techniques become integrated into the clinical environment.

  16. Dose - Response Curves for Dicentrics and PCC Rings: Preparedness for Radiological Emergency in Thailand

    International Nuclear Information System (INIS)

    Rungsimaphorn, B.; Rerkamnuaychoke, B.; Sudprasert, W.

    2014-01-01

    Establishing in-vitro dose calibration curves is important for reconstruction of radiation dose in the exposed individuals. The aim of this pioneering work in Thailand was to generate dose-response curves using conventional biological dosimetry: dicentric chromosome assay (DCA) and premature chromosome condensation (PCC) assay. The peripheral blood lymphocytes were irradiated with 137 Cs at a dose rate of 0.652 Gy/min to doses of 0.1, 0.25, 0.5, 0.75, 1, 2, 3, 4 and 5 Gy for DCA technique, and 5, 10, 15, 20 and 25 Gy for PCC technique. The blood samples were cultured and processed following the standard procedure given by the IAEA with slight modifications. At least 500-1,000 metaphases or 100 dicentrics/ PCC rings were analyzed using an automated metaphase finder system. The yield of dicentrics with dose was fitted to a linear quadratic model using Chromosome Aberration Calculation Software (CABAS, version 2.0), whereas the dose-response curve of PCC rings was fitted to a linear relationship. These curves will be useful for in-vitro dose reconstruction and can support the preparedness for radiological emergency in the country.

  17. Determination of organ doses during radiological examinations and calculation of somatically significant dose

    International Nuclear Information System (INIS)

    Steiner, H.

    1980-01-01

    Examples are used to demonstrate that a shift in the point of emphasis is necessary with regard to radiation hazard in medicinal X-ray diagnosis. The parameters employed in this study to calculate somatic dose (SD) and somatically significant dose (SSD) may well be in need of modification; nevertheless the numerical estimation of SSD arrived at here appears to reflect the right order of magnitude for the estimation of somatic risk. The consideration of the threshold dose for somatic injury remains a problem. (orig./MG) [de

  18. ZZ RADDECAY, Decay Data Library for Radiological Assessment

    International Nuclear Information System (INIS)

    2000-01-01

    Description of program or function: - Format: special format defined in documentation. - Nuclides: 500 nuclides of interest in the nuclear fuel cycle, environmental problems, nuclear medicine, fusion reactor technology, and radiological protection assessment. - Origin: DLC-80/DRALIST. ZZ-RADDECAY is a data library of half-lives, radioactive daughter nuclides, probabilities per decay and decay product energies for alpha particles, positrons, electrons, X-rays, and gamma-rays. The current data base contains approximately 500 nuclides of interest in the nuclear fuel cycle, environmental problems, nuclear medicine, fusion reactor technology, and radiological protection assessment. RADIATION DECAY VERSION 2 March 1997: This application is being provided by Aptec as 'Freeware' with permission of the author Mr. Charles Hacker, Engineering and Applied Science, Griffith University, Australia

  19. Dose assessment at Bikini Atoll

    International Nuclear Information System (INIS)

    Robison, W.L.; Phillips, W.A.; Colsher, C.S.

    1977-01-01

    Bikini Atoll is one of two sites in the northern Marshall Islands that was used by the United States as testing grounds for the nuclear weapons program from 1946 to 1958. In 1969 a general cleanup began at Bikini Atoll. Subsistence crops, coconut and Pandanus fruit, were planted on Bikini and Eneu Islands, and housing was constructed on Bikini Island. A second phase of housing was planned for the interior of Bikini Island. Preliminary data indicated that external gamma doses in the interior of the island might be higher than in other parts of the island. Therefore, to select a second site for housing on the island with minimum external exposure, a survey of Bikini Atoll was conducted in June 1975. External gamma measurements were made on Bikini and Eneu Islands, and soil and vegetations samples collected to evaluate the potential doses via terrestrial food chains and inhalation. Estimates of potential dose via the marine food chain were based upon data collected on previous trips to the atoll. The terrestrial pathway contributes the greater percentage, external gamma exposure contributes the next highest, and inhalation and marine pathways contribute minor fractions of the total whole body and bone marrow doses. The radionuclides contributing the major fraction of the dose are 90 Sr and 137 Cs. All living patterns involving Bikini Island exceed federal guidelines for 30-yr population doses. The Eneu Island living pattern leads to doses that are slightly less than federal guidelines. All patterns evaluated for Bikini Atoll lead to higher doses than those on the southern islands at Enewetak Atoll

  20. Radiology

    International Nuclear Information System (INIS)

    Meyers, M.A.

    1989-01-01

    This paper reports on disease processes originating within the alimentary tract, may extend through the extraperitoneal spaces, and abnormalities primarily arising within other extraperitoneal sites may significantly affect the bowel. Symptoms and signs may be obscure, delayed, or nonspecific, and the area is generally not accessible to auscultation, palpation, or percussion. Radiologic evaluation thus plays a critical role

  1. Practical measurement of radiation dose in pediatric radiology: use of the dose-area product on digital fluoroscopy and neonatal chest radiographs

    International Nuclear Information System (INIS)

    Chateil, J.F.; Rouby, C.; Brun, M.; Labessan, C.; Diard, F.

    2004-01-01

    Purpose. Control of radiation dose in pediatric radiology requires knowledge of the reference levels for all examinations. These data are useful for daily quality assessment, but are not perfectly known for some radiographic examinations. The purpose of our study was to evaluate the dose related to voiding cysto-urethrograms (VCUG), upper GI (UGI) and intravenous urography (IVU). Neonatal chest radiographs in the intensive care unit were also evaluated. Material and methods. For examinations with contrast material (478VCUG, 220UGI, 80IVU), the children were divided in groups based on their weight, from 5 to 30 Kg. Measurements were performed using an ionization chamber and expressed with the-dose-area product (DAP). For chest radiographs, a direct measurement of the entrance-skin dose was performed, with secondary calculation of the DAP. Results. For-VCUGs, the DAP ranged between 42.89 cGy.cm 2 and 125.41 cGy.cm 2 . The range was between 76.43, and 150.62 cGy.cm 2 for UGIs and between 49.06 and 83.33 cGy.cm 2 for IVUs. For neonate chest radiographs, DAP calculations were between 0.29 and 0.99 cGy.cm 2 . Conclusion. These values represent our reference doses. They allow continuous monitoring of our radiographic technical parameters and radiographic equipment and help to correct and improve them if necessary. (author)

  2. CP-50 calibration facility radiological safety assessment document

    International Nuclear Information System (INIS)

    Chilton, M.W.; Hill, R.L.; Eubank, B.F.

    1980-03-01

    The CP-50 Calibration Facility Radiological Safety Assessment document, prepared at the request of the Nevada Operations Office of the US Department of Energy to satisfy provisions of ERDA Manual Chapter 0531, presents design features, systems controls, and procedures used in the operation of the calibration facility. Site and facility characteristics and routine and non-routine operations, including hypothetical incidents or accidents are discussed and design factors, source control systems, and radiation monitoring considerations are described

  3. Radiological assessment of radioactive contamination on private clothing

    International Nuclear Information System (INIS)

    Schartmann, F.; Thierfeldt, S.

    2003-01-01

    In the very rare, cases where private clothing of persons working in a nuclear installation are inadvertently contaminated and this contamination is not detected when leaving the facility, there may be radiological consequences for this person as well as for members of his or her family. The VGB (Technische Vereinigung der Grosskraftwerksbetreiber) in Germany has investigated in detail the spread of contamination in nuclear power plants. Part of this evaluation programme was a radiological analysis which has been carried out by Brenk Systemplanung GmbH (Aachen/Germany). The radiological analysis started with the definition of the source term. It is highly unlikely that activities of more than 5 kBq 60 Co could leave a plant undetected on the body or the clothes. Nevertheless activities up to 50 kBq and different nuclide vectors were regarded. It has been found that 60 Co is the most important contaminant. The radiological analysis focusses on two types of contamination: particles and surface contamination. The pathways by which such a contamination can lead to an exposure by external irradiation or by ingestion depend on the type of contamination and are analysed in detail. For example, a particle could be retained in pockets or other parts of clothing and may lead to prolonged external irradiation until the piece of clothing is washed. The analysis is performed on the basis of conservative to realistic assumptions. In conclusion, the analysis has shown that especially particle contamination needs to be focussed on. However, by the advanced detection equipment in German plants doses which may pose a health hazard can safely be excluded. (authors)

  4. Dose audit for patients undergoing two common radiography examinations with digital radiology systems

    Science.gov (United States)

    İnal, Tolga; Ataç, Gökçe

    2014-01-01

    PURPOSE We aimed to determine the radiation doses delivered to patients undergoing general examinations using computed or digital radiography systems in Turkey. MATERIALS AND METHODS Radiographs of 20 patients undergoing posteroanterior chest X-ray and of 20 patients undergoing anteroposterior kidney-ureter-bladder radiography were evaluated in five X-ray rooms at four local hospitals in the Ankara region. Currently, almost all radiology departments in Turkey have switched from conventional radiography systems to computed radiography or digital radiography systems. Patient dose was measured for both systems. The results were compared with published diagnostic reference levels (DRLs) from the European Union and International Atomic Energy Agency. RESULTS The average entrance surface doses (ESDs) for chest examinations exceeded established international DRLs at two of the X-ray rooms in a hospital with computed radiography. All of the other ESD measurements were approximately equal to or below the DRLs for both examinations in all of the remaining hospitals. Improper adjustment of the exposure parameters, uncalibrated automatic exposure control systems, and failure of the technologists to choose exposure parameters properly were problems we noticed during the study. CONCLUSION This study is an initial attempt at establishing local DRL values for digital radiography systems, and will provide a benchmark so that the authorities can establish reference dose levels for diagnostic radiology in Turkey. PMID:24317331

  5. Dose audit for patients undergoing two common radiography examinations with digital radiology systems.

    Science.gov (United States)

    İnal, Tolga; Ataç, Gökçe

    2014-01-01

    We aimed to determine the radiation doses delivered to patients undergoing general examinations using computed or digital radiography systems in Turkey. Radiographs of 20 patients undergoing posteroanterior chest X-ray and of 20 patients undergoing anteroposterior kidney-ureter-bladder radiography were evaluated in five X-ray rooms at four local hospitals in the Ankara region. Currently, almost all radiology departments in Turkey have switched from conventional radiography systems to computed radiography or digital radiography systems. Patient dose was measured for both systems. The results were compared with published diagnostic reference levels (DRLs) from the European Union and International Atomic Energy Agency. The average entrance surface doses (ESDs) for chest examinations exceeded established international DRLs at two of the X-ray rooms in a hospital with computed radiography. All of the other ESD measurements were approximately equal to or below the DRLs for both examinations in all of the remaining hospitals. Improper adjustment of the exposure parameters, uncalibrated automatic exposure control systems, and failure of the technologists to choose exposure parameters properly were problems we noticed during the study. This study is an initial attempt at establishing local DRL values for digital radiography systems, and will provide a benchmark so that the authorities can establish reference dose levels for diagnostic radiology in Turkey.

  6. Evaluation of entrance skin dose to the skull in diagnostic radiology

    International Nuclear Information System (INIS)

    Mohamed, Anas Ali Elbushari

    2015-12-01

    Diagnostic x-ray radiology is a common diagnostic practice.Despite of its increasing hazard to human beings, imaging procedures should be achieved with less radiation dose and sufficient image quality. The aim of this study was to estimate the entrance skin dose(ESD) for patients undergoing selected diagnostic x-ray examinations in four hospitals.The study included the examinations of the skull; posterior- anterior(PA) and lateral projections. Fifty patients were enrolled in this study. ESDs were estimated from patients specific exposure parameters using established relation between output (μGy/mAs) and tube voltage(kVp). The estimated ESDs ranged from 0.0097-0.1846 mGy for skull (PA), 0.0097-0.1399 mGy for skull (LAT). These values were acceptable as compared with the international reference dose levels. This study provides additional data that can help the regulatory authority to establish reference dose levels for diagnostic radiology in Sudan.(Author)

  7. Evaluation of radiological protection and dose of skin entrance in paediatric dentistry examinations

    International Nuclear Information System (INIS)

    Khoury, Helen Jamil; Silveira, Marcia Maria Fonseca da; Couto, Geraldo Bosco Lindoso; Brasileiro, Izabela Vanderley

    2005-01-01

    In this work the radiological protection conditions and dose at the entrance of pediatric patients undergoing dental intraoral radiographs were evaluated. The study was conducted in two clinics of the dentistry course at the Federal University of Pernambuco, Recife, PB, Brazil, equipped with conventional X-ray apparatus, with 60 and 70 kV. 254 exams of 113 patients between the ages of 3 to 12 years were evaluated. The skin entrance dose was estimated using TLD-100 thermoluminescent dosemeters. During the examination were also recorded information regarding the time of exposure, radiographic technique used, use of thyroid protectors and lead apron, angle and distance of the cone Locator to the patient's skin. The results showed that the input skin doses ranged from 0.3 mGy to 10mGy. The lead apron was used in 71% of exams while the thyroid shield was only used in 58% of the exams. The exposure times ranged from 0,5s to 1,5s. From the results it can be concluded that the radiological procedures are not optimized and that in some cases the patient dose is high.

  8. A computerized assessment and response system for radiological emergency at Diablo Canyon Nuclear Power Plant

    International Nuclear Information System (INIS)

    Shih, C.C.; Thuillier, R.H.

    1984-01-01

    The U.S. Nuclear Regulatory Commission requires that nuclear power plants provide for rapid assessment and response in the event of a radiological emergency. At the Diablo Canyon Nuclear Power Plant, Pacific Gas and Electric Company uses a system of linked central minicomputer, satellite desktop computers and microprocessors to provide decision makers with timely and pertinent information in emergency situations. The system provides for data acquisition and microprocessing at meteorological and radiological monitoring sites. Current estimates or projections of offsite dose commitment are made in real-time by a dispersion/dose calculation model. Computerized dissemination of data and calculational results to decision makers at the government and utility levels is also available. The basic system in use is a commercially available Emergency Assessment and Response System (EARS). This generic system has been modified in-house to meet requirements specific to emergency situations at the plant. Distinctive features of the modification program includes: a highly professional man-machine interaction; consideration of site-specific factors; simulation of environmental radiology for development of drill scenarios; and concise, pertinent reports as input to decision making

  9. Preliminary radiological safety assessment for decommissioning of thoria dissolver of the 233U pilot plant, Trombay

    International Nuclear Information System (INIS)

    Priya, S.; Srinivasan, P.; Gopalakrishnan, R. K.

    2012-01-01

    The thoria dissolver, used for separation of 233 U from reactor-irradiated thorium metal and thorium oxide rods, is no longer operational. It was decided to carry out assessment of the radiological status of the dissolver cell for planning of the future decommissioning/dismantling operations. The dissolver interiors are expected to be contaminated with the dissolution remains of irradiated thorium oxide rods in addition to some of the partially dissolved thoria pellets. Hence, 220 Rn, a daughter product of 228 Th is of major radiological concern. Airborne activity of thoron daughters 212 Pb (Th-B) and 212 Bi (Th-C) was estimated by air sampling followed by high-resolution gamma spectrometry of filter papers. By measuring the full-energy peaks counts in the energy windows of 212 Pb, 212 Bi and 208 Tl, concentrations of thoron progeny in the sampled air were estimated by applying the respective intrinsic peak efficiency factors and suitable correction factors for the equilibration effects of 212 Pb and 212 Bi in the filter paper during the delay between sampling and counting. Then the thoron working level (TWL) was evaluated using the International Commission on Radiological Protection (ICRP) methodology. Finally, the potential effective dose to the workers, due to inhalation of thoron and its progeny during dismantling operations was assessed by using dose conversion factors recommended by ICRP. Analysis of filter papers showed a maximum airborne thoron progeny concentration of 30 TWLs inside the dissolver. (authors)

  10. Staff extremity doses in interventional radiology. Results of the ORAMED measurement campaign

    International Nuclear Information System (INIS)

    Nikodemová, D.; Brodecki, M.; Carinou, E.; Domienik, J.; Donadille, L.; Koukorava, C.; Krim, S.; Ruiz-López, N.; Sans-Merce, M.; Struelens, L.; Vanhavere, F.; Zaknoune, R.

    2011-01-01

    The introduction of interventional radiology (IR) procedures in the 20th century has demonstrated significant advantages over surgery procedures. As a result, their number is continuously rising in diagnostic, as well as, in therapy field and is connected with progress in highly sophisticated equipment used for these purposes. Nowadays, in the European countries more than 400 fluoroscopically guided IR procedures were identified with a 10–12% increase in the number of IR examinations every year (). Depending on the complexity of the different types of the interventions large differences in the radiation doses of the staff are observed. The staff that carries out IR procedures is likely to receive relatively high radiation doses, because IR procedures require the operator to remain close to the patient and close to the primary radiation beam. In spite of the fact that the operator is shielded by protective apron, the hands, eyes and legs remain practically unshielded. For this reason, one of the aims of the ORAMED project was to provide a set of standardized data on extremity doses for the personnel that are involved in IR procedures and to optimize their protection by evaluating the various factors that affect the doses. In the framework of work package 1 of the ORAMED project the impact of protective equipment, tube configuration and access routes were analyzed for the selected IR procedures. The position of maximum dose measured is also investigated. The results of the extremity doses in IR workplaces are presented in this study together with the influence of the above mentioned parameters on the doses. -- Highlights: ► We present a set of data on extremity doses for staff in selected interventional radiology procedures. ► We studied the influence of different parameters. ► The measured doses are analyzed according to the operators skill,his position during work, tube configuration, etc. ► Maximum doses recorded for all types of embolisation, in all

  11. AGING FACILITY WORKER DOSE ASSESSMENT

    International Nuclear Information System (INIS)

    R.L. Thacker

    2005-01-01

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

  12. Assessment of dose received by organ in lumbosacral examination

    International Nuclear Information System (INIS)

    Eltyeib, Nashwa Kheirallah

    2014-11-01

    The biological damage produced by radiation is closely related to the amount of energy absorbed in the case x- rays. Measurement of produced ionizing provides a useful assessment of the total energy absorbed. This study was performed in Khartoum Teaching Hospital in period of January to June 2014. This study was performed to assess the effective dose (ED) received in lumbosacral radiography examination and to analyze effective dose distributions among radiological department under study. The study was performed in Khartoum Teaching Hospital, covering two x-ray units and a sample of 50 patients. The following parameters were recorded: age weight, height, body mass index (BMI) derived from mass (kg) and (height. (m)) and exposure factors. The dose was measured for lumbosacral x- rays examination. For effective dose calculation, the entrance surface dose (ESD) values were estimated from the x-ray tube output parameters for lumbosacral spine A P and lateral examinations. The ED values were then calculated from the obtained ESD values using IAEA calculation methods. Effective doses were than calculated from energy imported using ED conversion factors by IAEA. The results of ED values calculated showed that patient exposures were within the normal range of exposure. The mean ED values calculated were (2.49 ±0.03) mGy and (5.5.60 ± 0.0.22) mGy for Lumbosacral spine A P and lateral examinations, respectively. Further studies are recommended with more number of patients and using more modalities for comparison.(Author)

  13. Evaluation of radionuclide levels and radiological dose in three populations of marine mammals in the eastern Canadian Arctic

    International Nuclear Information System (INIS)

    Macdonald, C.R.; Ewing, L.L.; Wiewel, A.M.; Harris, D.A.; Stewart, R.E.A.

    1993-01-01

    Radionuclide levels were measured in beluga, walrus and ringed seal populations collected in 1992 to assess radiation dose and changes in dose with age and sex. The authors hypothesized that Arctic marine food chains accumulate high levels of naturally-occurring radionuclides such as polonium-210 and that radiation may pose a stress to animals which also accumulate metals such as cadmium. Liver, kidney, muscle and jawbone were analyzed by gamma spectrometry for cesium-137, cesium-134, lead-210, potassium-40 and radium-226 and fission-derived nuclides. Polonium-210 was analyzed by alpha spec after autodeposition onto a silver disk. Cesium-137 concentrations in muscle in all three populations were low, and ranged from below detection limits to 10 Bq/kg ww. There was no evidence of fission-derived radionuclides such as zinc-65 or cobalt-60. Lead-210 levels ranged from below detection limits in muscle of ringed seal and walrus to a mean of 82.3 Bq/kg ww in walrus bone. Polonium-210 in the three population ranged from 10 to 30 Bq/kg ww in bone and kidney. The major contributor to dose in the animals was polonium-210 because it is an alpha emitter and accumulates to moderate levels in liver and kidney. Radiological dose is approximately 20--30 times higher than background in humans, and is considerably lower than the dose observed in terrestrial food chains in the Arctic

  14. Tennessee Valley region study: potential year 2000 radiological dose to population resulting from nuclear facility operations

    International Nuclear Information System (INIS)

    1978-06-01

    A companion report, DOE/ET-0064/1, presents a geographic, cultural, and demographic profile of the Tennessee Valley Region study area. This report describes the calculations of radionuclide release and transport and of the resultant dose to the regional population, assuming a projected installed capacity of 220,000 MW in the year 2000, of which 144,000 MW would be nuclear. All elements of the fuel cycle were assumed to be in operation. The radiological dose was calculated as a one-year dose based on ingestion of 35 different food types as well as for nine non-food pathways, and was reported as dose to the total body and for six specific organs for each of four age groups (infant, child, teen, and adult). Results indicate that the average individual would receive an incremental dose of 7 x 10 -4 millirems in the year 2000 from the operation of nuclear facilities within and adjacent to the region, five orders of magnitude smaller than the dose from naturally occurring radiation in the area. The major contributor to dose was found to be tritium, and the most significant pathways were immersion in air, inhalation of air, transpiration of tritium (absorption through the skin), and exposure radionuclide-containing soil. 60 references

  15. Howard Hughes Medical Institute dose assessment survey

    International Nuclear Information System (INIS)

    O'Brien, S.L.; McDougall, M.M.; Barkley, W.E.

    1996-01-01

    Biomedical science researchers often express frustration that health physics practices vary widely between individual institutions. A survey examining both internal and external dose assessment practices was devised and mailed to fifty institutions supporting biomedical science research. The results indicate that health physics dose assessment practices and policies are highly variable. Factors which may contribute to the degree of variation are discussed. 2 tabs

  16. The leaded apron revisited: does it reduce gonadal radiation dose in dental radiology

    Energy Technology Data Exchange (ETDEWEB)

    Wood, R.E.; Harris, A.M.; van der Merwe, E.J.; Nortje, C.J. (Ontario Cancer Institute, Princess Margaret Hospital, Toronto (Canada))

    1991-05-01

    A tissue-equivalent anthropomorphic human phantom was used with a lithium fluoride thermoluminescent dosimetry system to evaluate the radiation absorbed dose to the ovarian and testicular region during dental radiologic procedures. Measurements were made with and without personal lead shielding devices consisting of thyroid collar and apron of 0.25 mm lead thickness equivalence. The radiation absorbed dose with or without lead shielding did not differ significantly from control dosimeters in vertex occlusal and periapical views (p greater than 0.05). Personal lead shielding devices did reduce gonadal dose in the case of accidental exposure (p less than 0.05). A leaded apron of 0.25 mm lead thickness equivalent was permeable to radiation in direct exposure testing.

  17. The leaded apron revisited: does it reduce gonadal radiation dose in dental radiology

    International Nuclear Information System (INIS)

    Wood, R.E.; Harris, A.M.; van der Merwe, E.J.; Nortje, C.J.

    1991-01-01

    A tissue-equivalent anthropomorphic human phantom was used with a lithium fluoride thermoluminescent dosimetry system to evaluate the radiation absorbed dose to the ovarian and testicular region during dental radiologic procedures. Measurements were made with and without personal lead shielding devices consisting of thyroid collar and apron of 0.25 mm lead thickness equivalence. The radiation absorbed dose with or without lead shielding did not differ significantly from control dosimeters in vertex occlusal and periapical views (p greater than 0.05). Personal lead shielding devices did reduce gonadal dose in the case of accidental exposure (p less than 0.05). A leaded apron of 0.25 mm lead thickness equivalent was permeable to radiation in direct exposure testing

  18. Automatic management system for dose parameters in interventional radiology and cardiology

    International Nuclear Information System (INIS)

    Ten, J. I.; Fernandez, J. M.; Vano, E.

    2011-01-01

    The purpose of this work was to develop an automatic management system to archive and analyse the major study parameters and patient doses for fluoroscopy guided procedures performed in cardiology and interventional radiology systems. The X-ray systems used for this trial have the capability to export at the end of the procedure and via e-mail the technical parameters of the study and the patient dose values. An application was developed to query and retrieve from a mail server, all study reports sent by the imaging modality and store them on a Microsoft SQL Server data base. The results from 3538 interventional study reports generated by 7 interventional systems were processed. In the case of some technical parameters and patient doses, alarms were added to receive malfunction alerts so as to immediately take appropriate corrective actions. (authors)

  19. Automatic management system for dose parameters in interventional radiology and cardiology.

    Science.gov (United States)

    Ten, J I; Fernandez, J M; Vaño, E

    2011-09-01

    The purpose of this work was to develop an automatic management system to archive and analyse the major study parameters and patient doses for fluoroscopy guided procedures performed in cardiology and interventional radiology systems. The X-ray systems used for this trial have the capability to export at the end of the procedure and via e-mail the technical parameters of the study and the patient dose values. An application was developed to query and retrieve from a mail server, all study reports sent by the imaging modality and store them on a Microsoft SQL Server data base. The results from 3538 interventional study reports generated by 7 interventional systems were processed. In the case of some technical parameters and patient doses, alarms were added to receive malfunction alerts so as to immediately take appropriate corrective actions.

  20. Workplace-based assessment in radiology-where to now?

    Energy Technology Data Exchange (ETDEWEB)

    Augustine, K. [Department of Radiology, Southmead Hospital, North Bristol NHS Trust, Bristol BS10 5NB (United Kingdom); McCoubrie, P., E-mail: paul.mccoubrie@nbt.nhs.u [Department of Radiology, Southmead Hospital, North Bristol NHS Trust, Bristol BS10 5NB (United Kingdom); Wilkinson, J.R. [Department of Cardiology, St Bartholomew' s Hospital, London (United Kingdom); McKnight, L. [Department of Radiology, Morriston Hospital, Swansea (United Kingdom)

    2010-04-15

    Assessment of doctors is in a state of flux. Traditional methods of assessment have been critically examined and found inherently limited. The wholesale shift towards outcome-orientated education in the last 10 years has led to the relatively rapid development of a radically different method of assessment. This method focuses on assessing what doctors do in everyday practice rather than written or practical simulations. Known collectively as 'workplace-based assessment' tools, these have been embraced in North America, whereas they have been more cautiously adopted in the UK. However, many of these assessment tools have not been rigorously studied and, moreover, few have been specifically developed for assessing radiologists. However, they are likely to be incorporated into radiology training in the near future. This paper critically analyses both the underpinning assumptions behind this method and the evidence behind existing tools, and looks at the work that is required to develop, adopt or adapt such tools for use in radiology.

  1. Assessment of the radiological conditions in areas of Kuwait with residues of depleted uranium

    International Nuclear Information System (INIS)

    Cabianca, T.; Danesi, P.R.; Linsley, G.

    2004-01-01

    The 1991 Gulf War was the first conflict in which DU munitions were used extensively. After this conflict, questions arose regarding the possible link between exposure to ionizing radiation from DU and harmful biological effects. In view of these concerns, the Government of Kuwait, in February 2001, requested the IAEA to conduct an assessment to evaluate the possible radiological impact of residues of DU munitions from the 1991 Gulf War at 11 locations in Kuwait. For this purpose, the IAEA assembled a team of senior experts, who visited Kuwait in September 2001 to carry out a preliminary assessment of the sites and to evaluate the available information. In February 2002 scientists from the IAEA, the Spiez Laboratory (Switzerland), representing UNEP, and the Radiation Protection Department of the Ministry of Health of Kuwait, carried out a sampling campaign at these sites. Around 200 environmental samples, including soil, water and vegetation, were collected during the campaign and subsequently analysed. This study constitutes the first comprehensive radiological assessment of compliance with international radiation protection criteria and standards for areas with residues of DU munitions conducted under the auspices of the IAEA. The findings of this investigation indicate that DU does not pose a radiological hazard to the population of Kuwait. Annual radiation doses arising from exposure to DU residues would be of a few micro-sieverts, well below the annual doses from natural sources of radiation and far below the reference level recommended by the IAEA as a criterion to help establish whether remedial actions are necessary. DU penetrators can still be found at some of the locations visited. Prolonged skin contact with these residues is the only possible pathway that could result in exposures of radiological significance. As long as access to these areas remains restricted, the likelihood that members of the public could come into contact with these residues is low

  2. Dose reduction in diagnostic radiology. Proceedings of the Hospital Physicists' Association meeting on 8th December 1983 at Birbeck College, London

    International Nuclear Information System (INIS)

    Brennen, S.E.; Putney, R.G.

    1984-01-01

    Nine chapters review the Proceedings of the Hospital Physicists' Association Meeting held in London in 1983 on 'Dose Reduction in Diagnostic Radiology'. Among the topics discussed were the balance between dose reduction and image quality, various procedures and techniques for keeping the dose to the patient to a minimum including the use of K-edge filtration and rare-earth intensifying screens, equipment for assessing the area exposure product in patients and the balance between radiation risk and benefit from radiographic examinations. All nine chapters are indexed separately. (U.K.)

  3. Assessing Expertise in Radiology : Evaluating and Improving the Assessment of Knowledge and Image Interpretation Skill

    NARCIS (Netherlands)

    Ravesloot, C.J.

    2016-01-01

    Aim: Expert radiologists are excellent image interpreters. Unfortunately, image interpretation errors are frequent even among experienced radiologists and not much is known about which factors lead to expertise. Increasing assessment quality can improve radiological performance. Progress tests can

  4. Assessment of radiological risk in vicinity of former uranium mining areas in Poland

    Energy Technology Data Exchange (ETDEWEB)

    Ciupek, K.; Krajewski, P.; Kardas, M.; Suplinska, M. [Central Laboratory for Radiological Protection (Poland)

    2014-07-01

    The work carried out under the project NCBiR - 'Technologies Supporting Development of Safe Nuclear Power Engineering'; Task 3: Meeting the Polish nuclear power engineering's demand for fuel - fundamental aspects. Human activities related to the use of ionizing radiation and radioactive substances might cause exposure of the population and the environment. However, radiological risk assessment is mainly conducted only to human as an estimation of the effective dose being the sum of external and internal exposure whereas environmental protection assessment is more complex studies. The increased interest in recent years in this aspect and the ability to perform computer simulations contributed the development of models enabling assessment of exposure to certain organisms and estimation the concentrations of radionuclides in the various components of the environment. These models define a possible transition path of radionuclide in the atmosphere or waterways through their physical parameterization. The estimation of the content of radionuclides in plants, animals and human is possible by applying an existing risk assessment methodology. Models assessing human and environmental exposure from natural and artificial radionuclides, such as CROM, RESRAD, IMPACT or ERICA, come to be useful tools not only for researchers but also for regulatory authorities. This case study focused on the uranium mining areas (inactive mines and waste dumps) in the Giant Mountains (Karkonosze Mountains) in the south-west of Poland. On the basis of activity concentrations in samples of soil and mineral material from mine shafts, water samples from ponds, streams and small rivers and vegetation samples, an assessment of radiological impact of the former uranium mining areas was performed. The doses for reference group of inhabitants and biota in the vicinity of the former uranium mine were evaluated using IMPACT (EcoMetrix Inc.) model and ERICA tool. The variability and

  5. EMP Attachment 3 DOE-SC PNNL Site Dose Assessment Guidance

    Energy Technology Data Exchange (ETDEWEB)

    Snyder, Sandra F.

    2011-12-21

    This Dose Assessment Guidance (DAG) describes methods to use to determine the Maximally-Exposed Individual (MEI) location and to estimate dose impact to that individual under the U.S. Department of Energy Office of Science (DOE-SC) Pacific Northwest National Laboratory (PNNL) Site Environmental Monitoring Plan (EMP). This guidance applies to public dose from radioactive material releases to the air from PNNL Site operations. This document is an attachment to the Pacific Northwest National Laboratory (PNNL) Environmental Monitoring Plan (EMP) and describes dose assessment guidance for radiological air emissions. The impact of radiological air emissions from the U.S. Department of Energy Office of Science (DOE-SC) PNNL Site is indicated by dose estimates to a maximally exposed member of the public, referred to as the maximally exposed individual (MEI). Reporting requirements associated with dose to members of the public from radiological air emissions are in 40 CFR Part 61.94, WAC 246-247-080, and DOE Order 458.1. The DOE Order and state standards for dose from radioactive air emissions are consistent with U.S. Environmental Protection Agency (EPA) dose standards in 40 CFR 61.92 (i.e., 10 mrem/yr to a MEI). Despite the fact that the current Contract Requirements Document (CRD) for the DOE-SC PNNL Site operations does not include the requirement to meet DOE CRD 458.1, paragraph 2.b, public dose limits, the DOE dose limits would be met when EPA limits are met.

  6. Estimation of staff lens doses during interventional procedures. Comparing cardiology, neuroradiology and interventional radiology.

    Science.gov (United States)

    Vano, E; Sanchez, R M; Fernandez, J M

    2015-07-01

    The purpose of this article is to estimate lens doses using over apron active personal dosemeters in interventional catheterisation laboratories (cardiology IC, neuroradiology IN and radiology IR) and to investigate correlations between occupational lens doses and patient doses. Active electronic personal dosemeters placed over the lead apron were used on a sample of 204 IC procedures, 274 IN and 220 IR (all performed at the same university hospital). Patient dose values (kerma area product) were also recorded to evaluate correlations with occupational doses. Operators used the ceiling-suspended screen in most cases. The median and third quartile values of equivalent dose Hp(10) per procedure measured over the apron for IC, IN and IR resulted, respectively, in 21/67, 19/44 and 24/54 µSv. Patient dose values (median/third quartile) were 75/128, 83/176 and 61/159 Gy cm(2), respectively. The median ratios for dosemeters worn over the apron by operators (protected by the ceiling-suspended screen) and patient doses were 0.36; 0.21 and 0.46 µSv Gy(-1) cm(-2), respectively. With the conservative approach used (lens doses estimated from the over apron chest dosemeter) we came to the conclusion that more than 800 procedures y(-1) and per operator were necessary to reach the new lens dose limit for the three interventional specialties. © The Author 2015. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  7. Review at Bikini Atoll. Assessing radiological conditions at Bikini Atoll and the prospects for resettlement

    International Nuclear Information System (INIS)

    Stegnar, P.

    1998-01-01

    Some testing during the development of the atomic bomb was done in countries that do not have the infrastructure and expertise for evaluating any associated radiation risks. In such cases, outside expertise is needed to obtain independent advice about the radiological situation caused by residual radioactive material from nuclear testing. The IAEA has been requested by the governments of a number of its Member States to provide assistance in this context. Among the former nuclear test sites which the IAEA has reviewed is the Bikini Atoll of the Marshall Islands. Based on its review, the IAEA Advisory Group determined that no further corroboration of the measurements and assessments of the radiological conditions at Bikini Atoll is necessary. The data that have been collected are of sufficient quality to allow an appropriate evaluation to be performed. The limited IAEA monitoring of the area provided a good quality assurance verification of the previously collected data. It was recommended that Bikini Island should not be permanently resettled under the present radiological conditions. This recommendation was based on the assumption that persons resettling on the island would consume a diet of entirely locally produced food. The radiological data support that if a diet of this type were permitted, it could lead to an annual effective dose of about 15 mSv. This level was judged to require intervention of some type for radiation protection purposes

  8. Assessment of organ equivalent doses and effective doses from diagnostic X-ray examinations

    International Nuclear Information System (INIS)

    Park, Sang Hyun

    2003-02-01

    The MIRD-type adult male, female and age 10 phantoms were constructed to evaluate organ equivalent dose and effective dose of patient due to typical diagnostic X-ray examination. These phantoms were constructed with external and internal dimensions of Korean. The X-ray energy spectra were generated with SPEC78. MCNP4B ,the general-purposed Monte Carlo code, was used. Information of chest PA , chest LAT, and abdomen AP diagnostic X-ray procedures was collected on the protocol of domestic hospitals. The results showed that patients pick up approximate 0.02 to 0.18 mSv of effective dose from a single chest PA examination, and 0.01 to 0.19 mSv from a chest LAT examination depending on the ages. From an abdomen AP examination, patients pick up 0.17 to 1.40 mSv of effective dose. Exposure time, organ depth from the entrance surface and X-ray beam field coverage considerably affect the resulting doses. Deviation among medical institutions is somewhat high, and this indicated that medical institutions should interchange their information and the need of education for medical staff. The methodology and the established system can be applied, with some expansion, to dose assessment for other medical procedures accompanying radiation exposure of patients like nuclear medicine or therapeutic radiology

  9. A radiological accident consequence assessment system for Hong Kong

    International Nuclear Information System (INIS)

    Wong, M.C.; Lam, H.K.

    1993-01-01

    An account is given of the Hong Kong Radiological Accident Consequence Assessment System which would be used to assess the potential consequences of an emergency situation involving atmospheric release of radioactive material. The system has the capability to acquire real-time meteorological information from the Observatory's network of automatic stations, synoptic stations in the nearby region as well as forecast data from numerical prediction models. The system makes use of these data to simulate the transport and dispersion of the released radioactive material. The effectiveness of protective action on the local population is also modeled. The system serves as a powerful aid in the protective action recommendation processes

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

    International Nuclear Information System (INIS)

    Bayou, Teshome.

    1991-01-01

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

  11. Radiological impact assessment of the domestic on-road transportation of radioactive isotope wastes

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Myung Hwan; Hong, Sung Wook; Park, Jin Beak [Korea Radioactive Waste Agency, Technology Institute, Daejeon (Korea, Republic of)

    2016-09-15

    Korea Radioactive Waste Agency (KORAD) began to operate the low and intermediate level radioactive waste disposal facility in Gyeongju and to transport the radioactive waste containing radioactive isotopes from Daejeon to the disposal facility for the first time at 2015. For this radioactive waste transportation, in this study, radiological impact assessment is carried out for workers and public. The dose rate to workers and public during the transportation is estimated with consideration of the transportation scenarios and is compared with the Korean regulatory limit. The sensitivity analysis is carried out by considering both the variation of release ratios of the radioactive isotopes from the waste and the variation of the distances between the radioactive waste drum and worker during loading and unloading of radioactive waste. As for all the transportation scenarios, radiological impacts for workers and public have met the regulatory limits.

  12. Automated size-specific CT dose monitoring program: Assessing variability in CT dose

    International Nuclear Information System (INIS)

    Christianson, Olav; Li Xiang; Frush, Donald; Samei, Ehsan

    2012-01-01

    Purpose: The potential health risks associated with low levels of ionizing radiation have created a movement in the radiology community to optimize computed tomography (CT) imaging protocols to use the lowest radiation dose possible without compromising the diagnostic usefulness of the images. Despite efforts to use appropriate and consistent radiation doses, studies suggest that a great deal of variability in radiation dose exists both within and between institutions for CT imaging. In this context, the authors have developed an automated size-specific radiation dose monitoring program for CT and used this program to assess variability in size-adjusted effective dose from CT imaging. Methods: The authors radiation dose monitoring program operates on an independent health insurance portability and accountability act compliant dosimetry server. Digital imaging and communication in medicine routing software is used to isolate dose report screen captures and scout images for all incoming CT studies. Effective dose conversion factors (k-factors) are determined based on the protocol and optical character recognition is used to extract the CT dose index and dose-length product. The patient's thickness is obtained by applying an adaptive thresholding algorithm to the scout images and is used to calculate the size-adjusted effective dose (ED adj ). The radiation dose monitoring program was used to collect data on 6351 CT studies from three scanner models (GE Lightspeed Pro 16, GE Lightspeed VCT, and GE Definition CT750 HD) and two institutions over a one-month period and to analyze the variability in ED adj between scanner models and across institutions. Results: No significant difference was found between computer measurements of patient thickness and observer measurements (p= 0.17), and the average difference between the two methods was less than 4%. Applying the size correction resulted in ED adj that differed by up to 44% from effective dose estimates that were not

  13. Automated size-specific CT dose monitoring program: Assessing variability in CT dose

    Energy Technology Data Exchange (ETDEWEB)

    Christianson, Olav; Li Xiang; Frush, Donald; Samei, Ehsan [Clinical Imaging Physics Group, Department of Radiology, Duke University Medical Center, Durham, North Carolina 27705 and Department of Radiology, Duke University Medical Center, Durham, North Carolina 27705 (United States); Clinical Imaging Physics Group, Department of Radiology, Duke University Medical Center, Durham, North Carolina 27705 (United States); Department of Radiology, Duke University Medical Center, Durham, North Carolina 27705 (United States) and Carl E. Ravin Advanced Imaging Laboratories, Department of Radiology, Duke University Medical Center, Durham, North Carolina 27705 (United States); Department of Radiology, Duke University Medical Center, Durham, North Carolina 27705 (United States); Clinical Imaging Physics Group, Department of Radiology, Duke University Medical Center, Durham, North Carolina 27705 (United States); Department of Radiology, Duke University Medical Center, Durham, North Carolina 27705 (United States); Carl E. Ravin Advanced Imaging Laboratories, Department of Radiology, Duke University Medical Center, Durham, North Carolina 27705 (United States); Medical Physics Graduate Program, Duke University, Durham, North Carolina 27705 (United States); Department of Physics, Duke University, Durham, North Carolina 27710 (United States); and Department of Biomedical Engineering, Duke University, Durham, North Carolina 27708 (United States)

    2012-11-15

    Purpose: The potential health risks associated with low levels of ionizing radiation have created a movement in the radiology community to optimize computed tomography (CT) imaging protocols to use the lowest radiation dose possible without compromising the diagnostic usefulness of the images. Despite efforts to use appropriate and consistent radiation doses, studies suggest that a great deal of variability in radiation dose exists both within and between institutions for CT imaging. In this context, the authors have developed an automated size-specific radiation dose monitoring program for CT and used this program to assess variability in size-adjusted effective dose from CT imaging. Methods: The authors radiation dose monitoring program operates on an independent health insurance portability and accountability act compliant dosimetry server. Digital imaging and communication in medicine routing software is used to isolate dose report screen captures and scout images for all incoming CT studies. Effective dose conversion factors (k-factors) are determined based on the protocol and optical character recognition is used to extract the CT dose index and dose-length product. The patient's thickness is obtained by applying an adaptive thresholding algorithm to the scout images and is used to calculate the size-adjusted effective dose (ED{sub adj}). The radiation dose monitoring program was used to collect data on 6351 CT studies from three scanner models (GE Lightspeed Pro 16, GE Lightspeed VCT, and GE Definition CT750 HD) and two institutions over a one-month period and to analyze the variability in ED{sub adj} between scanner models and across institutions. Results: No significant difference was found between computer measurements of patient thickness and observer measurements (p= 0.17), and the average difference between the two methods was less than 4%. Applying the size correction resulted in ED{sub adj} that differed by up to 44% from effective dose

  14. Parameter calculation tool for the application of radiological dose projection codes

    International Nuclear Information System (INIS)

    Galindo G, I. F.; Vergara del C, J. A.; Galvan A, S. J.; Tijerina S, F.

    2016-09-01

    The use of specialized codes to estimate the radiation dose projection to an emergency postulated event at a nuclear power plant requires that certain plant data be available according to the event being simulated. The calculation of the possible radiological release is the critical activity to carry out the emergency actions. However, not all of the plant data required are obtained directly from the plant but need to be calculated. In this paper we present a computational tool that calculates the plant data required to use the radiological dose estimation codes. The tool provides the required information when there is a gas emergency venting event in the primary containment atmosphere, whether well or dry well and also calculates the time in which the spent fuel pool would be discovered in the event of a leak of water on some of the walls or floor of the pool. The tool developed has mathematical models for the processes involved such as: compressible flow in pipes considering area change and for constant area, taking into account the effects of friction and for the case of the spent fuel pool hydraulic models to calculate the time in which a container is emptied. The models implemented in the tool are validated with data from the literature for simulated cases. The results with the tool are very similar to those of reference. This tool will also be very supportive so that in postulated emergency cases can use the radiological dose estimation codes to adequately and efficiently determine the actions to be taken in a way that affects as little as possible. (Author)

  15. New concepts in risk assessment for patients with radiological treatment

    International Nuclear Information System (INIS)

    Tautz, M.; Brandt, G.A.

    1986-01-01

    In radiation risk assessment it must be differentiated between somatic and genetic effect on the one hand as well as between stochastic and non-stochastic effect on the other. According to definitions of the ICRP report 26 the limit for the dose equivalent of all tissues prevents non-stochastic radiation effects. With stochastic radiation effects probably exist no threshold doses; therefore the ALARA principle must be applied concerning radiation protection. The individual risk by stochastic radiation effects in its linear, linear-quadratic and quadratic extrapolations, respectively, is discussed in detail. The effective stochastic dose equivalent (H/sub eff/) as well as collective dose and collective damage are outlined

  16. Skin dose assessment in routine personnel beta/gamma dosimetry

    International Nuclear Information System (INIS)

    Christensen, P.

    1980-01-01

    The