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

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)

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

Stockholm Safety Conference. Analysis of the sessions on radiological protection, licensing and risk assessment

International Nuclear Information System (INIS)

Gea, A.

1981-01-01

A summary of the sessions on radiological protection, licensing and risk assessment in the safety conference of Stockholm is presented. It is considered the new point of view of the nuclear safety, probabilistic analysis, components failures probability and accident analysis. They are included conclusions applicable in many cases to development countries. (author)

Estimation of Radiological Terrorism Risk by Administrative Districts

Energy Technology Data Exchange (ETDEWEB)

Kim, Suk Hoon; Kim, Ju Youl [Seoul National Univ., Seoul (Korea, Republic of); Yoo, Ho Sik [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

2008-10-15

Since the 9/11 attack in USA, the threat of terrorism across the world has dramatically increased. Accordingly, estimating terrorism risk has become an essential part of catastrophe risk strategies throughout the world. There are many forms of terrorism. Recently, the prospect of the radiological terrorist attack using the radioactive material is considered as one of the most serious threats. The aim of this paper is to assess the radiological terrorism risk by administrative districts based on the parameters that imply threat, vulnerability, and consequences of terrorist attacks.

Estimation of Radiological Terrorism Risk by Administrative Districts

International Nuclear Information System (INIS)

Kim, Suk Hoon; Kim, Ju Youl; Yoo, Ho Sik

2008-01-01

Since the 9/11 attack in USA, the threat of terrorism across the world has dramatically increased. Accordingly, estimating terrorism risk has become an essential part of catastrophe risk strategies throughout the world. There are many forms of terrorism. Recently, the prospect of the radiological terrorist attack using the radioactive material is considered as one of the most serious threats. The aim of this paper is to assess the radiological terrorism risk by administrative districts based on the parameters that imply threat, vulnerability, and consequences of terrorist attacks

Radiation risk assessment in professionals working in dental radiology area using buccal micronucleus cytome assay.

Science.gov (United States)

Sadatullah, Syed; Dawasaz, Ali Azhar; Luqman, Master; Assiry, Ali A; Almeshari, Ahmed A; Togoo, Rafi Ahmad

2013-11-01

The aim of this study was to assess the incidence of micronuclei (MN) in buccal mucosal cells of professionals working in radiology area to determine the risk of stochastic effects of radiation. All the professionals and students working in King Khalid University - College of Dentistry radiology area were included in the Risk Group (RG = 27). The Control Group (CG = 27) comprised of healthy individual matching the gender and age of the RG. Buccal mucosal scraping from all the 54 subjects of RG and CG were stained with Papanicolaou stain and observed under oil immersion lens (×100) for the presence of micronuclei (MN) in the exfoliated epithelial cells. There was no significant difference between the incidence of MN in RG and CG (p = >0.05) using t-test. Routine radiation protection protocol does minimize the risk of radiation induced cytotoxicity, however, screening of professionals should be carried out at regular intervals.

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

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

The Symbiose project: an integrated framework for performing environmental radiological risk assessment

International Nuclear Information System (INIS)

Gonze, M.A.; Mourlon, C.; Garcia-Sanchez, L.; Beaugelin, K.; Chen, T.; Le Dizes, S.

2004-01-01

Human health and ecological risk assessments usually require the integration of a wide range of environmental data and modelling approaches, with a varying level of detail dependent on the management objectives, the complexity of the site and the level of ignorance about the pollutant behaviour/toxicity. Like most scientists and assessors did it recently, we recognized the need for developing comprehensive, integrated and flexible approaches to risk assessment. To meet these needs, IRSN launched the Symbiose project (2002-2006) which aims first, at designing a framework for integrating and managing data, methods and knowledge of some relevance in radiological risk to humans/biota assessment studies, and second, at implementing this framework in an information management, modelling and calculation platform. Feasibility developments (currently completed) led to the specification of a fully integrated, object-oriented and hierarchical approach for describing the fate, transport and effect of radionuclides in spatially-distributed environmental systems. This innovative approach has then been implemented in a platform prototype, main components of which are a user-friendly and modular simulation environment (e.g. using GoldSim toolbox), and a hierarchical object-oriented biosphere database. Both conceptual and technical developments will be presented here. (author)

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

Risk assessment on hazards for decommissioning safety of a nuclear facility

International Nuclear Information System (INIS)

Jeong, Kwan-Seong; Lee, Kune-Woo; Lim, Hyeon-Kyo

2010-01-01

A decommissioning plan should be followed by a qualitative and quantitative safety assessment of it. The safety assessment of a decommissioning plan is applied to identify the potential (radiological and non-radiological) hazards and risks. Radiological and non-radiological hazards arise during decommissioning activities. The non-radiological or industrial hazards to which workers are subjected during a decommissioning and dismantling process may be greater than those experienced during an operational lifetime of a facility. Workers need to be protected by eliminating or reducing the radiological and non-radiological hazards that may arise during routine decommissioning activities and as well as during accidents. The risk assessment method was developed by using risk matrix and fuzzy inference logic, on the basis of the radiological and non-radiological hazards for a decommissioning safety of a nuclear facility. Fuzzy inference of radiological and non-radiological hazards performs a mapping from radiological and non-radiological hazards to risk matrix. Defuzzification of radiological and non-radiological hazards is the conversion of risk matrix and priorities to the maximum criterion method and the mean criterion method. In the end, a composite risk assessment methodology, to rank the risk level on radiological and non-radiological hazards of the decommissioning tasks and to prioritize on the risk level of the decommissioning tasks, by simultaneously combining radiological and non-radiological hazards, was developed.

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

Introduction to CRRIS: a computerized radiological risk investigation system for assessing atmospheric releases of radionuclides

International Nuclear Information System (INIS)

Baes, C.F. III; Miller, C.W.; Kocher, D.C.; Sjoreen, A.L.; Murphy, B.D.

1985-08-01

The CRRIS is a Computerized Radiological Risk Investigation System consisting of eight fully integrated computer codes which calculate environmental transport of atmospheric releases of radionuclides and resulting doses and health risks to individuals or populations. Each code may also be used alone for various assessment applications. Radionuclides are handled by the CRRIS either in terms of the released radionuclides or the exposure radionuclides which consist of both the released nuclides and decay products that grow in during environmental transport. The CRRIS is not designed to simulate short-term effects. 51 refs

The use of importance sampling in a trial assessment to obtain converged estimates of radiological risk

International Nuclear Information System (INIS)

Johnson, K.; Lucas, R.

1986-12-01

In developing a methodology for assessing potential sites for the disposal of radioactive wastes, the Department of the Environment has conducted a series of trial assessment exercises. In order to produce converged estimates of radiological risk using the SYVAC A/C simulation system an efficient sampling procedure is required. Previous work has demonstrated that importance sampling can substantially increase sampling efficiency. This study used importance sampling to produce converged estimates of risk for the first DoE trial assessment. Four major nuclide chains were analysed. In each case importance sampling produced converged risk estimates with between 10 and 170 times fewer runs of the SYVAC A/C model. This increase in sampling efficiency can reduce the total elapsed time required to obtain a converged estimate of risk from one nuclide chain by a factor of 20. The results of this study suggests that the use of importance sampling could reduce the elapsed time required to perform a risk assessment of a potential site by a factor of ten. (author)

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)

Comparison of the distribution of non-radiological and radiological fatal risk in Ontario industries (addendum)

International Nuclear Information System (INIS)

Davis, C.K.; Forbes, W.F.; Hayward, L.M.

1986-09-01

Occupational limits for exposure to ionizing radiation, in force in Canada, are based on recommendations of international bodies, particularly the International Commission on Radiological Protection (ICRP). To determine whether the ICRP assertions concerning the similarity of the distributions of occupational risk at the higher risk levels (from non-radiation and from radiation work) to Canada a study of the high end of the distributions of non-radiological risk of occupational fatalities in the province of Ontario was performed. For the present study total doses from exposure to sources of ionizing radiation for Ontario workers were converted to relative risk rates to allow direct comparison with the non-radiological results. In addition, absolute values for the radiological risk rates (RRR) were derived. The radiological risk estimates are based on workers who work both from nuclear reactions and from X-rays. The conclusion is made that the radiological and non-radiological risk rate (NRRR) distributions are similar in shape, but the RRR are approximately 1 to 27 percent of the NRRR, depending on the industry concerned

Risk versus benefit in radiology

International Nuclear Information System (INIS)

Samuel, E.

1985-01-01

The risks of radiology may be grouped into a) those inherent in the use of ionizing radiation which today are well known and b) those associated with the use of any scientific method in medicine. Inherent risks of scientific methods like inadequate examination and the interpretation of results are discussed. Radiology brought major benefits in medical care and some of the newer methods are considered

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

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

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

Relative radiological risks derived from different TENORM wastes in Malaysia.

Science.gov (United States)

Ismail, B; Teng, I L; Muhammad Samudi, Y

2011-11-01

In Malaysia technologically enhanced naturally occurring radioactive materials (TENORM) wastes are mainly the product of the oil and gas industry and mineral processing. Among these TENORM wastes are tin tailing, tin slag, gypsum and oil sludge. Mineral processing and oil and gas industries produce large volume of TENORM wastes that has become a radiological concern to the authorities. A study was carried out to assess the radiological risk related to workers working at these disposal sites and landfills as well as to the members of the public should these areas be developed for future land use. Radiological risk was assessed based on the magnitude of radiation hazard, effective dose rates and excess cancer risks. Effective dose rates and excess cancer risks were estimated using RESRAD 6.4 computer code. All data on the activity concentrations of NORM in wastes and sludges used in this study were obtained from the Atomic Energy Licensing Board, Malaysia, and they were collected over a period of between 5 and 10 y. Results obtained showed that there was a wide range in the total activity concentrations (TAC) of nuclides in the TENORM wastes. With the exception of tin slag and tin tailing-based TENORM wastes, all other TENORM wastes have TAC values comparable to that of Malaysia's soil. Occupational Effective Dose Rates estimated in all landfill areas were lower than the 20 mSv y(-1) permissible dose limit. The average Excess Cancer Risk Coefficient was estimated to be 2.77×10(-3) risk per mSv. The effective dose rates for residents living on gypsum and oil sludge-based TENORM wastes landfills were estimated to be lower than the permissible dose limit for members of the public, and was also comparable to that of the average Malaysia's ordinary soils. The average excess cancer risk coefficient was estimated to be 3.19×10(-3) risk per mSv. Results obtained suggest that gypsum and oil sludge-based TENORM wastes should be exempted from any radiological regulatory

Relative radiological risks derived from different TENORM wastes in Malaysia

International Nuclear Information System (INIS)

Ismail, B.; Teng, I. L.; Muhammad samudi, Y.

2011-01-01

In Malaysia technologically enhanced naturally occurring radioactive materials (TENORM) wastes are mainly the product of the oil and gas industry and mineral processing. Among these TENORM wastes are tin tailing, tin slag, gypsum and oil sludge. Mineral processing and oil and gas industries produce large volume of TENORM wastes that has become a radiological concern to the authorities. A study was carried out to assess the radiological risk related to workers working at these disposal sites and landfills as well as to the members of the public should these areas be developed for future land use. Radiological risk was assessed based on the magnitude of radiation hazard, effective dose rates and excess cancer risks. Effective dose rates and excess cancer risks were estimated using RESRAD 6.4 computer code. All data on the activity concentrations of NORM in wastes and sludges used in this study were obtained from the Atomic Energy Licensing Board (Malaysia), and they were collected over a period of between 5 and 10 y. Results obtained showed that there was a wide range in the total activity concentrations (TAC) of nuclides in the TENORM wastes. With the exception of tin slag and tin tailing-based TENORM wastes, all other TENORM wastes have TAC values comparable to that of Malaysia's soil. Occupational Effective Dose Rates estimated in all landfill areas were lower than the 20 mSv y -1 permissible dose limit. The average Excess Cancer Risk Coefficient was estimated to be 2.77 x 10 -3 risk per mSv. The effective dose rates for residents living on gypsum and oil sludge-based TENORM wastes landfills were estimated to be lower than the permissible dose limit for members of the public, and was also comparable to that of the average Malaysia's ordinary soils. The average excess cancer risk coefficient was estimated to be 3.19 x 10 -3 risk per mSv. Results obtained suggest that gypsum and oil sludge-based TENORM wastes should be exempted from any radiological regulatory

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.

Radiological risk comparison guidelines

International Nuclear Information System (INIS)

Hallinan, E.J.; Muhlestein, L.D.; Brown, L.F.; Yoder, R.E.

1992-01-01

An important aspect of DOE safety analyses is estimating potential accident risk. The estimates are used to: determine if additional controls are needed, identify Safety Class Items, and demonstrate adequate risk reduction. Thus, guidelines are needed to measure comparative risks. The Westinghouse M ampersand O Nuclear Facility Safety Committee and the Safety Envelope Working Group have developed radiological risk guidelines for comparing the risks from individual accident analyses. These guidelines were prepared under contract with the US Department of Energy. These guidelines are based on historical DOE guidelines and current requirements, and satisfy DOE and technical community proposals. for goals that demonstrate acceptable risk. The guidelines consist of a frequency versus consequence curve for credible accidents. Offsite and onsite guidelines are presented. The offsite risk acceptance guidelines are presented in Figure 1. The guidelines are nearly isorisk for anticipated events where impacts are chronic, and provide additional reduction for unlikely events where impacts may be acute and risk uncertainties may be significant. The guidelines are applied to individual release accident scenarios where a discrete frequency and consequence has been estimated. The guideline curves are not to be used for total risk assessments. Common cause events are taken into consideration only for an individual facility. Frequencies outside the guideline range are considered to be local site option (analyst judgement) as far as assessments of risk acceptance are concerned. If the curve is exceeded, then options include either a more detailed analysis or imposing additional preventive or mitigative features. Another presentation discusses implementation in detail. Additional work is needed to provide risk comparison guidelines for releases from multiple facilities and for toxic releases

CRRIS: a computerized radiological risk-investigation system

International Nuclear Information System (INIS)

Baes, C.F. III; Miller, C.W.

1981-01-01

The US Environmental Protection Agency (EPA) is responsible for regulating radioactive airborne effluents in the US. A comprehensive, integrated Computerized Radiological Risk Investigation System (CRRIS) is being developed to support EPA's radiation standards development. This modular system consists primarily of five computer codes and their supporting data bases for estimating environmental transport and radiation doses and risks. Health effects are estimated on the basis of a life-table methodology developed by EPA. CRRIS is designed to provide EPA with a reasonable and flexible way of assessing the risk to man associated with radionuclide releases to the atmosphere

Availability and use of medical isotopes in Canada : performed as part of a radiological terrorism risk assessment. Technical memorandum

International Nuclear Information System (INIS)

Larsson, C.L.

2004-12-01

An assessment of the availability of radioactive material used for medical applications in Canada has been performed as part of the CBRN Research and Technology Initiative (CRTI) Project CRTI-02-0024RD (Probabilistic Risk Assessment Tool for Radiological Dispersal Devices). A general list of medical radioisotopes used worldwide was compiled via literature searches and Internet investigations. This list was then compared to all isotopes licenced to healthcare facilities in Canada. Sources of lesser concern for this study, such as noble gases, short-lived isotopes, and radioisotopes not licenced for medical applications in Canada, were eliminated. The remaining sources were then analysed for frequency of use and maximum licenced activity to assess which materials would be of highest concern in relation to radiological terrorism. A detailed description of the application, typical administered activity, and other relevant information for these most common and highest licenced activity medical sources was assembled to feed directly into the risk assessment database. A general discussion of security in healthcare facilities is also given. Due to the constant advances made in medicine, the information relating to licenced isotopes is dynamic and thus requires updating to ensure the database is kept current. (author)

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

Methodology to assess the radiological sensitivity of soils: Application to Spanish soils

International Nuclear Information System (INIS)

Trueba Alonso, C.

2005-01-01

A methodology, based on standard physical and chemical soil properties, has been developed to estimate the radiological sensitivity of soils to a 137 C s and 90 S r contamination. In this framework, the soil radiological sensitivity is defined as the soil capability to mobilise or to retain these radionuclides. The purpose of this methodology is to assess, in terms of radiological sensitivity indexes, the behaviour of 137 C s and 90 S r in soils and their fluxes to man, considering two exposure pathways, the external irradiation exposure and the internal exposure from ingestion. The methodology is applied to the great variety of soil types found in Spain, where the soil profile is the reference unit for the assessment. The results for these soil types show, that their basic soil properties are the key to categorise the radiological sensitivity according to the risks considered. The final categorisation allows to identify soils specially sensible and improves the radiological impact assessment predictions. (Author)

Principles and issues in radiological ecological risk assessment

International Nuclear Information System (INIS)

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

2003-01-01

This paper provides a bridge between the fields of ecological risk coefficients.variability o published particle-solution distribution coeffiissues identified in the US Department of Energy's Graded Approach fo 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

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)

Uranium Chemical and Radiological Risk Assessment for Freshwater Ecosystems Receiving Ore Mining Releases: Principles, Equations and Parameters

International Nuclear Information System (INIS)

Beaugelin-Seiller, K.; Garnier-Laplace, J.; Gilbin, R.; Adam, C.

2008-01-01

Uranium is an element that has the solely characteristic to behave as significant hazard both from a chemical and radiological point of view. Exclusively of natural occurrence, its distribution into the environment may be influenced by human activities, such as nuclear fuel cycle, military use of depleted uranium, or coal and phosphate fertilizer use, which finally may impact freshwater ecosystems. Until now, the associated environmental impact and risk assessments were conducted separately. We propose here to apply the same methodology to evaluate the ecological risk due to potential chemotoxicity and radiotoxicity of uranium. This methodology is articulated into the classical four steps (EC, 2003: problem formulation, effect and exposure analysis, risk characterisation). The problem formulation dealt both with uranium viewed as a chemical element and as the three isotopes 234, 235 and 238 of uranium and their main daughters. Then, the exposure analysis of non-human species was led on the basis of a common conceptual model of the fluxes occurring in freshwater ecosystems. No-effect values for the ecosystem were derived using the same effect data treatment in parallel. A Species Sensitivity Distribution was fitted: (1) to the ecotoxicity data sets illustrating uranium chemotoxicity and allowing the estimation of a Predicted-No-Effect-Concentration for uranium in water expressed in μg/L; (2) to radiotoxicity effect data as it was done within the ERICA project, allowing the estimation of a Predicted No-Effect-Dose-Rate (in μGy·h -1 ). Two methods were then applied to characterize the risk to the ecosystem: a screening method using the risk quotient approach, involving for the radiological aspect back calculation of the water limiting concentration from the PNEDR for each isotope taken into account and a probabilistic risk assessment. A former uranium ore mining case-study will help in demonstrating the application of the whole methodology

The radiological risks associated with the thorium fuelled HTGR fuel cycle. A comparative risk evaluation

International Nuclear Information System (INIS)

Dodd, D.H.; Hienen, J.F.A. van.

1995-10-01

This report presents the results of task B.3 of the 'Technology Assessment of the High Temperature Reactor' project. The objective of task B.3 was to evaluate the radiological risks to the general public associated with the sustainable HTGR cycle. Since the technologies to be used at several stages of this fuel cycle are still in the design phase and since a detailed specification of this fuel cycle has not yet been developed, the emphasis was on obtaining a global impression of the risk associated with a generic thorium-based HTGR fuel cycle. This impression was obtained by performing a comparative risk analysis on the basis of data given in the literature. As reference for the comparison a generic uranium fuelled LWR cycle was used. The major benefit with respect to the radiological rsiks of basing the fuel cycle around modular HTGR technology instead of the LWR technology is the increase in reactor safety. The design of the modular HTGR is expected to prevent the release of a significant amount of radioactive material to the environment, and hence early deaths in the surrounding population, during accident conditions. This implies that there is no group risk as defined in the Dutch risk management policy. The major benefit of thorium based fuel cycles over uranium based fuel cycles is the reduction in the radiological risks from unraium mining and milling. The other stages of the nuclear fuel cycle which make a significant contribution to the radiological risks are electricity generation, reprocessing and final disposal. The risks associated with the electricity generation stage are dominated by the risks from fission products, activated corrosion products and the activation products tritium and carbon-14. The risks associated with the reprocessing stage are determined by fission and activation products (including actinides). (orig./WL)

The radiological risks associated with the thorium fuelled HTGR fuel cycle. A comparative risk evaluation

Energy Technology Data Exchange (ETDEWEB)

Dodd, D.H.; Hienen, J.F.A. van

1995-10-01

This report presents the results of task B.3 of the `Technology Assessment of the High Temperature Reactor` project. The objective of task B.3 was to evaluate the radiological risks to the general public associated with the sustainable HTGR cycle. Since the technologies to be used at several stages of this fuel cycle are still in the design phase and since a detailed specification of this fuel cycle has not yet been developed, the emphasis was on obtaining a global impression of the risk associated with a generic thorium-based HTGR fuel cycle. This impression was obtained by performing a comparative risk analysis on the basis of data given in the literature. As reference for the comparison a generic uranium fuelled LWR cycle was used. The major benefit with respect to the radiological rsiks of basing the fuel cycle around modular HTGR technology instead of the LWR technology is the increase in reactor safety. The design of the modular HTGR is expected to prevent the release of a significant amount of radioactive material to the environment, and hence early deaths in the surrounding population, during accident conditions. This implies that there is no group risk as defined in the Dutch risk management policy. The major benefit of thorium based fuel cycles over uranium based fuel cycles is the reduction in the radiological risks from unraium mining and milling. The other stages of the nuclear fuel cycle which make a significant contribution to the radiological risks are electricity generation, reprocessing and final disposal. The risks associated with the electricity generation stage are dominated by the risks from fission products, activated corrosion products and the activation products tritium and carbon-14. The risks associated with the reprocessing stage are determined by fission and activation products (including actinides). (orig./WL).

Estimates of radiological risk from depleted uranium weapons in war scenarios.

Science.gov (United States)

Durante, Marco; Pugliese, Mariagabriella

2002-01-01

Several weapons used during the recent conflict in Yugoslavia contain depleted uranium, including missiles and armor-piercing incendiary rounds. Health concern is related to the use of these weapons, because of the heavy-metal toxicity and radioactivity of uranium. Although chemical toxicity is considered the more important source of health risk related to uranium, radiation exposure has been allegedly related to cancers among veterans of the Balkan conflict, and uranium munitions are a possible source of contamination in the environment. Actual measurements of radioactive contamination are needed to assess the risk. In this paper, a computer simulation is proposed to estimate radiological risk related to different exposure scenarios. Dose caused by inhalation of radioactive aerosols and ground contamination induced by Tomahawk missile impact are simulated using a Gaussian plume model (HOTSPOT code). Environmental contamination and committed dose to the population resident in contaminated areas are predicted by a food-web model (RESRAD code). Small values of committed effective dose equivalent appear to be associated with missile impacts (50-y CEDE radiological risk. These computer simulations suggest that little radiological risk is associated to the use of depleted uranium weapons.

Assessment of the radiological risks of road transport accidents involving type A package shipments

International Nuclear Information System (INIS)

Lange, F.; Fett, H.J.; Schwarz, G.; Raffestin, D.; Schneider, T.; Gelder, R.; Hughes, J.S.; Shaw, K.B.; Hedberg, B.; Simenstad, P.; Svahn, B.; Hienen, J.F.A.; Jansma, R.

1998-01-01

This paper is an account of work performed within a multi-lateral research project on the radiological risks associated with the transportation of Type A packaged radioactive material. The research project has been performed on behalf of the European Commission and various national agencies of the participating countries and involved organizations and institutes of five EU Member States, France, Germany, The Netherlands, Sweden, and the UK. The main objectives of the research project were the assessment and appraisal of the potential radiological risks of road transport accidents involving Type A package shipments in participating EU Member States. Data were collected and include harmonized sets information related to the type, quantity and characteristics of Type A package shipments by road. Such databases were basically non-existent until recently. The results are expected to be valuable to both national agencies and international organizations, with responsibilities for the safe transport of radioactive materials by providing some insight in the carriage of radioactive materials by road making up a major fraction of radioactive material transports. Similarly, a wide body of information has been collected and compiled on road transport accidents in terms of the frequency of occurrence and the severity of accidental impact loads potentially experienced by a Type A package.In addition, the results will facilitate judgement of the adequacy of the IAEA Transport Regulations as far as Type A packages are concerned. (O.M.)

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

EU-CIS joint study project 2. Intervention criteria in CIS, risk assessments and non-radiological factors in decision-making

Energy Technology Data Exchange (ETDEWEB)

Hedemann Jensen, P. [Risoe National Lab., Roskilde (Denmark); Demin, V.F. [Russian Reserch Centre `Kurchatov Inst.`, Moscow (Russian Federation); Konstantinov, Y.O. [Research Inst. of Radiation Hygiene, St. Petersburg (Russian Federation); Likhtarev, I.A. [Ukrainian Scientific Centre for Radiation Medicine, Kiev (Ukraine); Rolevich, I.V. [Chernobyl State Commiettee, Minsk (Belarus); Schneider, T. [Centre d`etudes sur l`Evaluation de la Protection dans le domaine Nucleaire, CEPN, Paris (France)

1996-05-01

An extensive radiation risk estimation methodology has recently been developed in Russia and used for estimates of risk in exposed populations in the republics of Russia, Belarus and Ukraine. Results based on demographic data for the three republics are presented and compared with risk estimates from the EU risk model ASQRAD. The intervention criteria in the CIS republics have been evolving since the Chernobyl accident. The development of criteria in each of the three republics has been analysed and the CIS-Criteria have been compared to international guidance on intervention. After a nuclear or radiological emergency both radiological and non-radiological protection factors will influence the level of protective actions being introduced. The role of non-radiological protection factors in the overall optimization of health protection is addressed. It is argued that optimization of the overall health protection is not a question of developing radiation radiation protection philosophy to fully include socio-psychological factors. It is rather a question of including these factors - in parallel with the radiological protection factors - in cooperation between radiation protection experts and psychological specialists under the responsibility of the decision maker. (au) 19 tabs., 10 ills., 45 refs.

EU-CIS joint study project 2. Intervention criteria in CIS, risk assessments and non-radiological factors in decision-making

International Nuclear Information System (INIS)

Hedemann Jensen, P.; Demin, V.F.; Konstantinov, Y.O.; Likhtarev, I.A.; Rolevich, I.V.; Schneider, T.

1996-05-01

An extensive radiation risk estimation methodology has recently been developed in Russia and used for estimates of risk in exposed populations in the republics of Russia, Belarus and Ukraine. Results based on demographic data for the three republics are presented and compared with risk estimates from the EU risk model ASQRAD. The intervention criteria in the CIS republics have been evolving since the Chernobyl accident. The development of criteria in each of the three republics has been analysed and the CIS-Criteria have been compared to international guidance on intervention. After a nuclear or radiological emergency both radiological and non-radiological protection factors will influence the level of protective actions being introduced. The role of non-radiological protection factors in the overall optimization of health protection is addressed. It is argued that optimization of the overall health protection is not a question of developing radiation radiation protection philosophy to fully include socio-psychological factors. It is rather a question of including these factors - in parallel with the radiological protection factors - in cooperation between radiation protection experts and psychological specialists under the responsibility of the decision maker. (au) 19 tabs., 10 ills., 45 refs

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

Probabilistic and possibilistic approach for assessment of radiological risk due to organically bound and tissue free water tritium

International Nuclear Information System (INIS)

Dahiya, Sudhir; Hegde, A.G.; Joshi, M.L.; Verma, P.C.; Kushwaha, H.S.

2006-01-01

This study illustrates use of two approaches namely probabilistic using Monte Carlo simulation (MCS) and possibilistic using fuzzy α-cut (FAC) to estimate the radiological cancer risk to the population from ingestion of organically bound tritium (OBT) and tissue free water tritium (TFWT) from fish consumption from the Rana Pratap Sagar Lake (RPSL), Kota. Using FAC technique, radiological cancer risk rate (year -1 ) at A αl.0 level were 1.15E-08 and 1.50E-09 for OBT and TFWT respectively from fish ingestion pathway. The radiological cancer risk rate (year -1 ) using MCS approach at 50th percentile (median) level is 1.14E-08 and 1.49E-09 for OBT and HTO respectively from ingestion of fresh water fish. (author)

Ecological risk assessment of mixtures of radiological and chemical stressors: Methodology to implement an msPAF approach

International Nuclear Information System (INIS)

Beaumelle, Léa; Della Vedova, Claire; Beaugelin-Seiller, Karine; Garnier-Laplace, Jacqueline; Gilbin, Rodolphe

2017-01-01

A main challenge in ecological risk assessment is to account for the impact of multiple stressors. Nuclear facilities can release both radiological and chemical stressors in the environment. This study is the first to apply species sensitivity distribution (SSD) combined with mixture models (concentration addition (CA) and independent action (IA)) to derive an integrated proxy of the ecological impact of combined radiological and chemical stressors: msPAF (multisubstance potentially affected fraction of species). The approach was tested on the routine liquid effluents from nuclear power plants that contain both radioactive and stable chemicals. The SSD of ionising radiation was significantly flatter than the SSD of 8 stable chemicals (namely Cr, Cu, Ni, Pb, Zn, B, chlorides and sulphates). This difference in shape had strong implications for the selection of the appropriate mixture model: contrarily to the general expectations the IA model gave more conservative (higher msPAF) results than the CA model. The msPAF approach was further used to rank the relative potential impact of radiological versus chemical stressors. - Highlights: • msPAF methodology was applied on mixtures of radiological and chemical stressors. • A consistent set of chronic SSDs was collected for ionising radiation and 8 stable chemicals. • The SSD of ionising radiation had lower steepness than the SSD of stable chemicals. • This resulted in higher msPAF values based on the IA than on the CA mixture model. - The msPAF approach combining SSD and mixture models was used for the first time on mixtures of radiological and chemical stressors.

Radiological risk assessment of isotope laboratories according to the requirements of the radiation protection ordinance and the protective labour legislation

International Nuclear Information System (INIS)

Stuerm, R.P.; Kuster, M.; Traub, K.

2001-01-01

According to the Swiss Radiation Safety Ordinance the supervising authority may require a safety report from the operator of a radioactive laboratory (Art.95) and establish the methodology of the risk analysis. Isotope laboratories of the chemical industry are supervised by Swiss accident insurance agency (SUVA). In that respect SUVA safeguards both radiation protection issues and general protection of the workers and established guide lines in order to assess conventional risks in industrial premises. In these conventional analysis the working process is analysed according to its possible detriment (death, severe invalidity, slight invalidity, injury with absence, injury without absence) and the probability of occurrence (frequent, seldom, rare, improbable, virtually impossible). According to this the risks are categorised in a matrix as 'high', 'medium' and 'low'. SUVA requested such a risk analysis for two isotope laboratories of B type in Basel in which on the one hand the hazard to the workers on the other hand to the public should be analysed and radiologically assessed. It was proposed to use a methodology established in workers safety and the insurance section. This required a comparison of risks of radiation doses in mSv to the consequences of conventional working accidents (death, invalidity) and the risk perception of the public and politicians. In this paper this risk matrix derived in discussions among the supervising body, the company management, the laboratory head and workers is described. In the opinion of the authors such a comparison between radiological and conventional risks has not been performed up to now and the results obtained here are open to discussion. (orig.) [de

Transportation radiological risk assessment for the programmatic environmental impact statement: An overview of methodologies, assumptions, and input parameters

International Nuclear Information System (INIS)

Monette, F.; Biwer, B.; LePoire, D.; Chen, S.Y.

1994-01-01

The U.S. Department of Energy is considering a broad range of alternatives for the future configuration of radioactive waste management at its network of facilities. Because the transportation of radioactive waste is an integral component of the management alternatives being considered, the estimated human health risks associated with both routine and accident transportation conditions must be assessed to allow a complete appraisal of the alternatives. This paper provides an overview of the technical approach being used to assess the radiological risks from the transportation of radioactive wastes. The approach presented employs the RADTRAN 4 computer code to estimate the collective population risk during routine and accident transportation conditions. Supplemental analyses are conducted using the RISKIND computer code to address areas of specific concern to individuals or population subgroups. RISKIND is used for estimating routine doses to maximally exposed individuals and for assessing the consequences of the most severe credible transportation accidents. The transportation risk assessment is designed to ensure -- through uniform and judicious selection of models, data, and assumptions -- that relative comparisons of risk among the various alternatives are meaningful. This is accomplished by uniformly applying common input parameters and assumptions to each waste type for all alternatives. The approach presented can be applied to all radioactive waste types and provides a consistent and comprehensive evaluation of transportation-related risk

Radiological assessment of 36Cl in the disposal of used CANDU fuel

International Nuclear Information System (INIS)

Johnson, L.H.; Goodwin, B.W.; Sheppard, S.C.; Tait, J.C.; Wuschke, D.M.; Davison, C.C.

1995-06-01

An assessment of the potential radiological impact of 36 Cl in the disposal of used CANDU fuel has been performed. The assessment was based on new data on chlorine impurity levels in used fuel. Data bases for the vault, geosphere, and biosphere models used in the EIS postclosure assessment case study (Goodwin et al. 1994) were modified to include the necessary 36 Cl data. The resulting safety analysis shows that estimated radiological risks from 36 Cl are forty times lower than from 129 I at 10 4 a; this, incorporation of 36 Cl into the models does not change the overall conclusions of the study of Goodwin et al. (1994a). For human intrusion scenarios, an analysis using the methodology of Wuschke (1992) showed that the maximum risk is unaffected by the inclusion of 36 Cl. (author). 51 refs., 5 tabs., 15 figs

Risk communication and radiological/nuclear terrorism: a strategic view.

Science.gov (United States)

Becker, Steven M

2011-11-01

It is now widely recognized that effective communication is a crucial element in radiological/nuclear terrorism preparedness. Whereas in the past, communication and information issues were sometimes viewed as secondary in comparison with technical concerns, today the need to improve risk communication, public information, and emergency messaging is seen as a high priority. The process of improving radiological/nuclear terrorism risk communication can be conceptualized as occurring in four overlapping phases. The first phase involves the recognition that communication and information issues will be pivotal in shaping how a radiological/nuclear terrorism incident unfolds and in determining its outcome. This recognition has helped shape the second phase, in which various research initiatives have been undertaken to provide an empirical basis for improved communication. In the third and most recent phase, government agencies, professional organizations and others have worked to translate research findings into better messages and informational materials. Like the first and second phases, the third phase is still unfolding. The fourth phase in risk communication for radiological/nuclear terrorism-a mature phase-is only now just beginning. Central to this phase is a developing understanding that for radiological/nuclear terrorism risk communication to be fully effective, it must go beyond crafting better messages and materials (as essential as that may be). This emerging fourth phase seeks to anchor radiological/nuclear communication in a broader approach: one that actively engages and partners with the public. In this article, each of the four stages is discussed, and future directions for improving radiological/nuclear terrorism risk communication are explored.

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)

Assessment of the radiological risks of road transport accidents involving Type A packages

International Nuclear Information System (INIS)

Lange, F.; Fett, H.J.; Schwarz, G.; Raffestin, D.; Schneider, T.; Gelder, R.; S. Hughes, J.; B. Shaw, K.; Hedberg, B.; Simenstad, P.; Svahn, B.; Heinen, J.F.A. van; Jansma, R.

2001-01-01

An assessment and evaluation of the potential radiological risks of transport accidents involving Type A package shipments by road have been performed by five EU Member States, France, Germany, Sweden, The Netherlands, and the UK. The analysis involved collection and analysis of information on a national basis related to the type, volume, and characteristics of Type A package consignments, the associated radioactive traffic, and the expected frequency and consequences of potential vehicular road transport accidents. It was found that the majority of Type A packaged radioactive material shipments by road is related to applications of non-special form radioactive material, i.e. radiopharmaceuticals, radiochemicals etc., in medicine, research, and industry and special form material contained in radiography and other radiation sources, e.g. gauging equipment. The annual volumes of Type A package shipments of radiopharmaceuticals and radiochemicals by road differ considerably between the participating EU Member States from about 12,000 Type A packages in Sweden to about 240,000 in the Netherlands. The broad range reflects to a large extent the supply of radioactive material for the national populations and the production and distribution operations prevailing in the participating EU Member States (some are producer countries, others are not!). Very few standard package designs weighing from about 1-25 kg are predominant in Type A package shipments in all participating countries. Type A packages contain typically a range of radioactivity from a few mega becquerels to a few tens of giga becquerels, the average package activity contents is in terms of fractions of A 2 about 0.01, i.e. about one hundredth of a Type A package contents limits. Based on a probabilistic risk assessment method it has been concluded that the expected frequencies of occurrence of vehicular road transport accidents with the potential to result in an environmental release - including radiologically

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)

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

Radiological risk perception in Spain

International Nuclear Information System (INIS)

Martinez-Arias, R.; Prades, A.; Meza, R.; Sola, R.

1997-01-01

How does society perceive radiation risks?. Is there any logic underlying those perceptions?.The article describes the results of a cross-cultural survey on radiological risk perception applied to a representative sample of the Spanish population. This study has been carried out in the framework of a research project subsidized by the European Union and the CSN. (Author) 16 refs

RESRAD: an analysis method of the exposure via to ionizing radiation, used on radiological risk assessment in sites with problems of soil contamination

International Nuclear Information System (INIS)

Oliveira Loureiro, C. de; Yu, C.

1995-01-01

A microcomputer program, denominated RESRAD, was presented and described as an analytical tool to perform pathway analysis and radiological risk assessment. Nine exposure pathways are implemented in the code. They are the following: external radiation; dust inhalation; inhalation of radon; and, ingestion of plant, meat, milk, water, aquatic food, and soil. The U.S. Department of Energy (US-DOE) has recommended the use of RESRAD, as a radiological risk assessment package, for completing the pathway analysis needed to derive specific soil-guidelines and to support the ALARA evaluation. Since its conception, the RESRAD code has been continuously improved and updated to accommodate comments and suggestions from its users and to incorporate new features to improve its capability and flexibility. Version 5.0 consolidates the last major RESRAD updates. The package is intentionally user-friendly and operates with a menu system from which the user can access the data input screens, run the RESRAD calculations and view the output. (author). 4 refs, 1 fig, 1 tab

The assessment of the safety and the radiological risks associated with the transport of radioactive wastes in Romania

International Nuclear Information System (INIS)

Vieru, G.

2000-01-01

Problems related to the handling, treatment, packaging, storage, transportation, and disposal of radioactive wastes (radwastes) are very important and the responsibility for the safe management of radioactive wastes for the protection of human health and the environment has long been recognized. Safety and public welfare are to be considered within the radioactive waste management, particularly in the field of transportation because of the potential risk that it could pose to the public and to the environment. The IAEA regulations ensure safety in the transport of Radioactive Materials (RAM) by laying down detailed requirements, appropriate to the degree of hazard represented by the respective material, taking into account its form and quantity. Risk assessment provides a basis for routing radwastes and developing mitigation plans, prioritizing initiatives and enacting legislation to protect human beings and the environment. Factors such as shipment cost, distance, population exposed, environmental impacts or sensitivity, time in transit and infrastructure related issues, could be included in the terms of safety and risk. The paper presents risk assessment activities aimed to evaluate risk categories and the radiological consequences that may arise during normal (accident free) transport and those resulting from transport accidents involving waste shipments in Romania. (author)

Radiological risks from irradiation of cargo contents with EURITRACK neutron inspection systems

International Nuclear Information System (INIS)

Giroletti, E.; Bonomi, G.; Donzella, A.; Viesti, G.; Zenoni, A.

2012-01-01

The radiological risk for the population related to the neutron irradiation of cargo containers with a tagged neutron inspection system has been studied. Two possible effects on the public health have been assessed: the modification of the nutritional and organoleptic properties of the irradiated materials, in particular foodstuff, and the neutron activation of consumer products (i.e. food and pharmaceuticals). The result of this study is that irradiation of food and foodstuff, pharmaceutical and medical devices in container cargoes would neither modify the properties of the irradiated material nor produce effective doses of concern for public health. Furthermore, the dose received by possible stowaways present inside the container during the inspection is less than the annual effective dose limit defined by European Legislation for the public. - Highlights: ► Neutron irradiation of cargo containers implies a radiological risk. ► The risk is about the modification of food properties and the products activation. ► Assessment is made about the EURITRACK neutron irradiation system. ► Results show that the EURITRACK scanning is not dangerous for the population.

Radioactivity, radiological risk and metal pollution assessment in marine sediments from Calabrian selected areas, southern Italy

Science.gov (United States)

Caridi, F.; Messina, M.; Faggio, G.; Santangelo, S.; Messina, G.; Belmusto, G.

2018-02-01

The two most significant categories of physical and chemical pollutants in sediments (radionuclides and metals) were investigated in this article, in order to evaluate pollution levels in marine sediments from eight different selected sites of the Calabria region, south of Italy. In particular samples were analyzed to determine natural and anthropic radioactivity and metal concentrations, in order to assess any possible radiological hazard, the level of contamination and the possible anthropogenic impact in the investigated area. Activity concentrations of 226Ra, 232Th, 40K and 137Cs were measured by High Purity Germanium (HPGe) gamma spectrometry. The obtained results show that, for radium (in secular equilibrium with uranium), the specific activity ranges from ( 14 ± 1) Bq/kg dry weight (d.w.) to ( 54 ± 9) Bq/kg d.w.; for thorium, from ( 12 ± 1) Bq/kg d.w. to ( 83 ± 8) Bq/kg d.w.; for potassium, from ( 470 ± 20) Bq/kg d.w. to ( 1000 ± 70) Bq/kg d.w. and for cesium it is lower than the minimum detectable activity value. The absorbed gamma dose rate in air (D), the annual effective dose equivalent (AEDE) outdoor and the external hazard index ( H_ex) were calculated to evaluate any possible radiological risk, mainly due to the use of marine sediments for the beach nourishment. The results show low levels of radioactivity, thus discarding any significant radiological risk. Some metals (As, Cd, Cr tot, Hg, Ni, Pb, Cu, Zn, Mn and Fe), that could be released into the environment by both natural and anthropogenic sources, were investigated through inductively coupled plasma mass spectrometry (ICP-MS) measurements and compared with the limits set by the Italian Legislation, to assess any possible contamination. Experimental results show that they are much lower than the contamination threshold value, thus excluding their presence as pollutants. The degree of sediment contaminations were quantified using enrichment factor ( EF) and geoaccumulation index ( I geo) for

Risks from dental radiology

International Nuclear Information System (INIS)

Costa, Tamara Goularte

2013-01-01

The objective of this research is to demonstrate the risks and consequences of exposure to dental X-ray. The methodology used was the survey of bibliographic literature on this matter. First, we tried to understand the operation and characteristics of dental X-rays. Afterwards, we tried to know about the risks that this procedure offers to workers and patients. And concluded with the consequences of such exposure. The results showed that dental x-rays only offer risks in prolonged exposure, can affect the worker or patient to pathologies such as cancer or a life-time decreased due to the stochastic effect. Therefore, radiological protection standards must be respected and practised. (author)

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)

Medicine and ionizing rays: a help sheet in analysing risks in exo-buccal dental radiology

International Nuclear Information System (INIS)

Gauron, C.

2009-01-01

This document proposes a synthesis of useful knowledge for radioprotection in the case of exo-buccal dental radiology. In the first part, several aspects are considered: the concerned personnel, the course of treatment procedures, the hazards, the identification of the risk associated with ionizing radiation, the risk assessment and the determination of exposure levels, the strategy to control the risks (reduction of risks, technical measures concerning the installation or the personnel, teaching and information, prevention and medical monitoring), and risk control assessment

Health Risks of Diagnostic Radiology

International Nuclear Information System (INIS)

Al-Oraby, M.N.A.

2014-01-01

Exposure to ionizing radiation during diagnostic radiologic procedures carries small but real risks. Children, young adults and pregnant women are especially vulnerable. Exposure of patients to diagnostic energy levels of ionizing radiation should be kept to the minimum necessary to provide useful clinical information and allay patients concerns about radiation-related risks. Computerized Tomography (CT) accounts for two thirds of the cumulative patient dose from diagnostic radiological procedures and the cumulative dose from CT is rising as technological advances increase the number of indications and the capabilities of CT. Carcinogenesis and teratogenesis are the main concerns with ionizing radiation. The risk increases as the radiation dose increases. There is no minimum threshold and the risk is cumulative: a dose of 1 mSv once a year for 10 years is equivalent to a single dose of 10 mSv. Whenever practical, choose an imaging test that uses less radiation or no radiation and lengthen the periods between follow-up imaging tests. Some patients may avoid screening mammography because of fear of radiation-induced cancer, yet this test uses a very small radiation dose (0.6 mSv, much less than the annual dose from background radiation, 3.6 mSv). (author)

Radiological assessment of {sup 36}Cl in the disposal of used CANDU fuel

Energy Technology Data Exchange (ETDEWEB)

Johnson, L H; Goodwin, B W; Sheppard, S C; Tait, J C; Wuschke, D M; Davison, C C

1995-06-01

An assessment of the potential radiological impact of {sup 36}Cl in the disposal of used CANDU fuel has been performed. The assessment was based on new data on chlorine impurity levels in used fuel. Data bases for the vault, geosphere, and biosphere models used in the EIS postclosure assessment case study (Goodwin et al. 1994) were modified to include the necessary {sup 36}Cl data. The resulting safety analysis shows that estimated radiological risks from {sup 36}Cl are forty times lower than from {sup 129}I at 10{sup 4} a; this, incorporation of {sup 36}Cl into the models does not change the overall conclusions of the study of Goodwin et al. (1994a). For human intrusion scenarios, an analysis using the methodology of Wuschke (1992) showed that the maximum risk is unaffected by the inclusion of {sup 36}Cl. (author). 51 refs., 5 tabs., 15 figs.

Safety analysis and risk assessment handbook

International Nuclear Information System (INIS)

Peterson, V.L.; Colwell, R.G.; Dickey, R.L.

1997-01-01

This Safety Analysis and Risk Assessment Handbook (SARAH) provides guidance to the safety analyst at the Rocky Flats Environmental Technology Site (RFETS) in the preparation of safety analyses and risk assessments. Although the older guidance (the Rocky Flats Risk Assessment Guide) continues to be used for updating the Final Safety Analysis Reports developed in the mid-1980s, this new guidance is used with all new authorization basis documents. With the mission change at RFETS came the need to establish new authorization basis documents for its facilities, whose functions had changed. The methodology and databases for performing the evaluations that support the new authorization basis documents had to be standardized, to avoid the use of different approaches and/or databases for similar accidents in different facilities. This handbook presents this new standardized approach. The handbook begins with a discussion of the requirements of the different types of authorization basis documents and how to choose the one appropriate for the facility to be evaluated. It then walks the analyst through the process of identifying all the potential hazards in the facility, classifying them, and choosing the ones that need to be analyzed further. It then discusses the methods for evaluating accident initiation and progression and covers the basic steps in a safety analysis, including consequence and frequency binning and risk ranking. The handbook lays out standardized approaches for determining the source terms of the various accidents (including airborne release fractions, leakpath factors, etc.), the atmospheric dispersion factors appropriate for Rocky Flats, and the methods for radiological and chemical consequence assessments. The radiological assessments use a radiological open-quotes templateclose quotes, a spreadsheet that incorporates the standard values of parameters, whereas the chemical assessments use the standard codes ARCHIE and ALOHA

Work procedures and risk factors for high rdiation exposure among radiologic technologists in South Korea

Energy Technology Data Exchange (ETDEWEB)

Kim, Jae Young; Choi, Yeong Chull [Dept. of Preventive Medicine, Keimyung University College of Medicine, Daegu (Korea, Republic of); Lee, Won Jin; Cha, Eun Shil [Dept. of Preventive Medicine, Korea University College of Medicine, Seoul (Korea, Republic of)

2016-12-15

Radiologic technologists currently consist of 31.5% among diagnostic radiation workers in South Korea. Among diagnostic radiation workers, radiologic technologists receive the highest annual and collective doses in South Korea. Comprehensive assessment of the work practices and associated radiation doses from diagnostic radiology procedures should be undertaken for effective prevention for radiologic technologists. Using the national survey, this study aimed (1) to explore the distribution of the work procedures performed by gender, (2) to evaluate occupational radiation exposure by work characteristics and safety compliance, (3) to identify the primary factors influencing high radiation exposure among radiologic technologists in South Korea. This study provided detailed information on work practices, number of procedures performed on weekly basis, and occupational radiation doses among radiologic technologists in South Korea. Average radiation dose for radiologic technologists is higher than other countries, and type of facility, work safety, and wearing lead apron explained quite a portion of increased risk in the association between radiology procedures and radiation exposure among radiologic technologists.

Work procedures and risk factors for high rdiation exposure among radiologic technologists in South Korea

International Nuclear Information System (INIS)

Kim, Jae Young; Choi, Yeong Chull; Lee, Won Jin; Cha, Eun Shil

2016-01-01

Radiologic technologists currently consist of 31.5% among diagnostic radiation workers in South Korea. Among diagnostic radiation workers, radiologic technologists receive the highest annual and collective doses in South Korea. Comprehensive assessment of the work practices and associated radiation doses from diagnostic radiology procedures should be undertaken for effective prevention for radiologic technologists. Using the national survey, this study aimed (1) to explore the distribution of the work procedures performed by gender, (2) to evaluate occupational radiation exposure by work characteristics and safety compliance, (3) to identify the primary factors influencing high radiation exposure among radiologic technologists in South Korea. This study provided detailed information on work practices, number of procedures performed on weekly basis, and occupational radiation doses among radiologic technologists in South Korea. Average radiation dose for radiologic technologists is higher than other countries, and type of facility, work safety, and wearing lead apron explained quite a portion of increased risk in the association between radiology procedures and radiation exposure among radiologic technologists.

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

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

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...

Radiological transportation risk assessment of the shipment of sodium-bonded fuel from the Fast Flux Test Facility to the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Green, J.R.

1995-01-01

This document was written in support of Environmental Assessment: Shutdown of the Fast Flux Test Facility (FFTF), Hanford Site, Richland, Washington. It analyzes the potential radiological risks associated with the transportation of sodium-bonded metal alloy and mixed carbide fuel from the FFTF on the Hanford Site in Washington State to the Idaho Engineering Laboratory in Idaho in the T-3 Cask. RADTRAN 4 is used for the analysis which addresses potential risk from normal transportation and hypothetical accident scenarios

Radiological transportation risk assessment of the shipment of sodium-bonded fuel from the Fast Flux Test Facility to the Idaho National Engineering Laboratory

Energy Technology Data Exchange (ETDEWEB)

Green, J.R.

1995-01-31

This document was written in support of Environmental Assessment: Shutdown of the Fast Flux Test Facility (FFTF), Hanford Site, Richland, Washington. It analyzes the potential radiological risks associated with the transportation of sodium-bonded metal alloy and mixed carbide fuel from the FFTF on the Hanford Site in Washington State to the Idaho Engineering Laboratory in Idaho in the T-3 Cask. RADTRAN 4 is used for the analysis which addresses potential risk from normal transportation and hypothetical accident scenarios.

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

Radiological risk in case of potential exposures

International Nuclear Information System (INIS)

Chiossi, C.E.

1998-01-01

This paper presents basic theoretical aspects about the probabilistic conception of radiological risk in case of potential exposure associated with practices concerning installations such as nuclear power plants, research reactors or repositories for final disposal of radioactive waste. It is here shown how such conception helps in the decision-making process concerning people protection in the frame of the above mentioned situations. The question of risk is first analysed in a general sense- be it radiological risk or not- showing common concepts among the different technical definitions of risk. The subjects of individual risk an societal risk are then considered, as well as that of risk perception. Finally, some probabilistic safety criteria are described- corresponding to different schools which study radioactive and nuclear installations safety- putting emphasis in the way how such criteria are used in the decision-making process in order to accept or reject an installation from the point of view of safety. The criteria referred to are the 'Farmer Limit-Line', the 'Single-Dual Failure Criterion' and the 'Argentine Acceptation Criterion', in particular this last one is carefully detailed showing its origin as well as its practical application. (author)

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.

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

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)

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.

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.

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

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

Risks and benefits of diagnostic radiology. A contribution to quality assurance

International Nuclear Information System (INIS)

Angerstein, W.

1995-01-01

After some introductory remarks on the necessity of determining quantitative standards in diagnostic radiology as one of the key subjects in medicine, the author discusses eight statistical quantities that describe and elucidate the activities in the subject field. These quantities establish a connection between parameters such as number of images, examinations, patients and the number of therapy-relevant diagnoses, false diagnoses and incidents, and establish a relationship to the collective dose as a value indicating the radiation dose and the number of radiation injuries. These quantities can in principle be derived as retrospective or prospective data. Knowledge of these quantities would indeed represent an essential contribution to assessing the value of diagnostic radiology, risks involved, and achievement of quality assurance goals. For a number of relevant quotients, the article gives concrete values derived on the basis of evaluation of data collected at various medical centers, or obtained from regional or Land statistics of the former GDR. These data and the collective dose to be computed in addition, allow to derive a quotient composed of the benefits and the risks of diagnostic radiology, giving the relationship between the number of therapy-relevant diagnoses and the number of casualties. The value of this quotient depends on the examination method applied and usually is between 1000 and more than 100 000, and thus is lower than the risk quotients calculated for other fields of medicine, or non-medical fields [de

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.

Radiological risk guidelines for nonreactor nuclear facilities at the Pacific Northwest Laboratory

International Nuclear Information System (INIS)

Lucas, D.E.; Ikenberry, T.A.

1993-09-01

Radiological risk evaluation guidelines for the public and workers have been developed at the Pacific Northwest Laboratory (PNL) based upon the Nuclear Safety Policy of the US Department of Energy (DOE) established in Secretary of Energy Notice SEN-35-91. The DOE nuclear safety policy states that the general public shall be protected such that no individual bears significant additional risk to health and safety from the operation of a DOE nuclear facility above the risks to which members of the general population are normally exposed. The radiological risk evaluation guidelines developed at PNL are unique in that they are (1) based upon quantitative risk goals and (2) provide a consistent level of risk management. These guidelines are used to evaluate the risk from radiological accidents that may occur during research and development activities at PNL, and are not intended for evaluation of routine exposures. A safety analyst uses the,frequency of the potential accident and the radiological dose to a given receptor to determine if the accident consequences meet the objectives of the Nuclear Safety Policy. The radiological risk evaluation guidelines are an effective tool for assisting in the management of risk at DOE nonreactor nuclear facilities. These guidelines (1) meet the nuclear safety policy of DOE, (2) establish a tool for managing risk at a consistent level within the defined constraints, and (3) set risk at an appropriate level, as compared with other risks encountered by the public and worker. Table S.1 summarizes the guidelines developed in this report

Radiological risk guidelines for nonreactor nuclear facilities at the Pacific Northwest Laboratory

International Nuclear Information System (INIS)

Lucas, D.E.; Ikenberry, T.A.

1994-03-01

Radiological risk evaluation guidelines for the public and workers have been developed at the Pacific Northwest Laboratory (PNL) based upon the Nuclear Safety Policy of the US Department of Energy (DOE) established in Secretary of Energy Notice SEN-35-91 (DOE 1991). The DOE nuclear safety policy states that the general public be protected-such that no individual bears significant additional risk to health and safety from the operation of a DOE nuclear facility above the risks to which members of the general population are normally exposed. The radiological risk evaluation guidelines developed at PNL are unique in that they are (1) based upon quantitative risk goals and (2) provide a consistent level of risk management. These guidelines are used to evaluate the risk from radiological accidents that may occur during research and development activities at PNL. A safety analyst uses the frequency of the potential accident and the radiological dose to a given receptor to determine if the accident consequences meet the objectives of the Nuclear Safety Policy

Estimating risk at a Superfund site contaminated with radiological and chemical wastes

International Nuclear Information System (INIS)

Temeshy, A.; Liedle, J.M.; Sims, L.M.; Efird, C.R.

1992-01-01

This paper describes the method and results for estimating carcinogenic and noncarcinogenic effects at a Superfund site that is radiologically and chemically contaminated. Risk to receptors from disposal of waste in soil and resulting contamination of groundwater, air, surface water, and sediment is quantified. Specific risk assessment components which are addressed are the exposure assessment, toxicity assessment, and the resulting risk characterization. In the exposure assessment, potential exposure pathways are identified using waste disposal inventory information for soil and modeled information for other media. Models are used to calculate future radionuclide concentrations in groundwater, soil, surface water and air. Chemical exposure concentrations are quantified using site characterization data. Models are used to determine concentrations of chemicals in surface water and in air. Toxicity parameters used to quantify the dose-response relationship associated with the carcinogenic contaminants are slope factors and with noncarcinogenic contaminants are reference doses. In the risk characterization step, results from the exposure assessment and toxicity assessment are summarized and integrated into quantitative risk estimates for carcinogens and hazard induces for noncarcinogens. Calculated risks for carcinogenic contaminants are compared with EPA's target risk range. At WAG 6, the risk from radionuclides and chemicals for an on-WAG homesteader exceeds EPA's target risk range. Hazard indices are compared to unity for noncarcinogenic contaminants. At WAG 6, the total pathway hazard index for the on-WAG homesteader exceeds unity

Determining cutoff distances for assessing risks from transportation accident radiation releases

International Nuclear Information System (INIS)

Sandquist, G.M.; Slaughter, D.M.; Kimura, C.Y.; Brumburgh, G.

1995-01-01

The transportation of radioactive materials throughout the United States and the world is a ubiquitous and sometimes controversial activity. Almost universally, these transportation activities have been performed without major incident, and the safety record for transportation of radioactive material is outstanding compared with the transportation of other hazardous materials. Nevertheless, concerns still exist regarding adequate regulation of radioactive material transportation and accurate assessment of the health risks associated with accidents. These concerns are addressed through certification by the cognizant regulatory authority over the transportation container or the performance of a transportation risk assessment. In a transportation risk assessment, accident situations are examined, frequencies are estimated, and consequences resulting from the accident are analyzed and evaluated for acceptance. A universal question with any transportation risk assessment that examines the radiological consequences from release accidents is, At what distance may the dispersion analysis be terminated? This paper examines cutoff distances and their consequences for assessing health risks from radiological transportation releases

Assessment of the radiological quality of tap waters 2008-2009

International Nuclear Information System (INIS)

Caamano, Delphine; Tracol, Raphael; Guillotin, Laetitia; Jedor, Beatrice; Davezac, Henri; Loyen, Jeanne

2011-06-01

After a recall of the context (radioactivity, origin of natural radioactivity in waters, exposure of population to natural radioactivity and health impact, indicators of water radiological quality, presence of uranium in water), this document reports a study which is based on the health control of water radiological quality by regional health agencies, on the analysis of natural and artificial radionuclides, on a survey on tap water radiological quality performed in 2009 by regional health agencies, and on an inventory of results related to the presence of radon in water performed by the IRSN and these agencies. The obtained results are presented and discussed in terms of factors impacting the result representativeness, of generalisation of the implementation of a health control, of tap water radiological quality. It is outlined that the uranium-related chemical risk is higher than the radiological risk

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)

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

Dosimetry on the radiological risks prevention in radiotherapy

International Nuclear Information System (INIS)

Fornet R, O. M.; Perez G, F.

2014-08-01

Dosimetry in its various forms plays a determining role on the radiological risks prevention in radiotherapy. To prove this in this paper is shown an analysis based on the risk matrix method, how the dosimetry can influence in each stages of a radiotherapy service; installation and acceptance, operation, maintenance and calibration. For each one of these stages the role that can play is analyzed as either the initiating event of a radiological accident or limiting barrier of these events of the dosimetric processes used for the individual dosimetry, the area monitoring, fixed or portable, for radiation beam dosimetry and of the patients for a radiotherapy service with cobalt-therapy equipment. The result of the study shows that the application of a prospective approach in the role evaluation of dosimetry in the prevention and mitigation of the consequences of a radiological accident in radiotherapy is crucial and should be subject to permanent evaluation at each development stage of these services. (author)

Management of radiological and non-radiological risks in a decommissioning project

International Nuclear Information System (INIS)

Deboodt, Pascal

2002-01-01

As already shown by Oudiz et al (1), the assessment of carcinogenic risk and the management of asbestos and ionising radiation needs to focus on three levels namely, the legal obligation level, the organisation and companies level and the work situation level. The main purpose of a paper is to provide a practical example of such management. Based on a set of four operations related to the removal of asbestos from working areas, we want to illustrate the general conclusions as presented in (1). After a short description of the SCK.CEN institution and of the BR3 decommissioning pilot project, we will present the general approach of the Health Physics and Safety at the SCK.CEN. Than, four sets of operations will be proposed. One should then stress on the driving forces and compare with the conclusions presented in (1). Lessons which have been learned will serve as conclusion, together with the remaining questions which are the questions the 4. European ALARA Network Workshop has to deal with. The examples which are presented here are certainly too limited for deriving general conclusions. The first remark we want to bring here deals with the importance of the communication at the different levels and at the different steps of the operations. Faced with unusual work circumstances, one certainly needs to develop adapted tools as far as communication is concerned. In this way, the level of the safety culture in the installations can act as a very efficient tool. A second topic, which has to be pointed out, is the commitment of all management levels. All the partners have been faced in their past to circumstances where they have to take decision. So they have built their know how and also their usual way of thinking and/or working. As a consequence of this, some resistance can exist and it is not only a question of good communication. Here, it has to do with the behaviour of people. One's has to cope with these resistances by use of an other behaviour. This requires a

Interventional radiography and mortality risks in U.S. radiologic technologists

Energy Technology Data Exchange (ETDEWEB)

Linet, Martha S.; Freedman, D.M.; Sigurdson, Alice J.; Doody, Michele M. [National Cancer Institute, Radiation Epidemiology Branch, Division of Cancer Epidemiology and Genetics, Bethesda, MD (United States); Hauptmann, Michael [National Cancer Institute, Biostatistics Branch, Division of Cancer Epidemiology and Genetics, Bethesda, MD (United States); Alexander, Bruce H. [University of Minnesota, Division of Environmental Health Sciences, Minneapolis, MN (United States); Miller, Jeremy [Information Management Services, Inc., Rockville, MD (United States)

2006-09-15

With the exponential increase in minimally invasive fluoroscopically guided interventional radiologic procedures, concern has increased about the health effects on staff and patients of radiation exposure from these procedures. There has been no systematic epidemiologic investigation to quantify serious disease risks or mortality. To quantify all-cause, circulatory system disease and cancer mortality risks in U.S. radiologic technologists who work with interventional radiographic procedures, we evaluated mortality risks in a nationwide cohort of 88,766 U.S. radiologic technologists (77% female) who completed a self-administered questionnaire during 1994-1998 and were followed through 31 December 2003. We obtained information on work experience, types of procedures (including fluoroscopically guided interventional procedures), and protective measures plus medical, family cancer history, lifestyle, and reproductive information. Cox proportional hazards regression models were used to compute relative risks (RRs) with 95% confidence intervals (CIs). Between completion of the questionnaire and the end of follow-up, there were 3,581 deaths, including 1,209 from malignancies and 979 from circulatory system diseases. Compared to radiologic technologists who never or rarely performed or assisted with fluoroscopically guided interventional procedures, all-cause mortality risks were not increased among those working on such procedures daily. Similarly, there was no increased risk of mortality resulting from all circulatory system diseases combined, all cancers combined, or female breast cancer among technologists who daily performed or assisted with fluoroscopically guided interventional procedures. Based on small numbers of deaths (n=151), there were non-significant excesses (40%-70%) in mortality from cerebrovascular disease among technologists ever working with these procedures. The absence of significantly elevated mortality risks in radiologic technologists reporting the

Developing RESRAD-BASELINE for environmental baseline risk assessment

International Nuclear Information System (INIS)

Cheng, Jing-Jy.

1995-01-01

RESRAD-BASELINE is a computer code developed at Argonne developed at Argonne National Laboratory for the US Department of Energy (DOE) to perform both radiological and chemical risk assessments. The code implements the baseline risk assessment guidance of the US Environmental Protection Agency (EPA 1989). The computer code calculates (1) radiation doses and cancer risks from exposure to radioactive materials, and (2) hazard indexes and cancer risks from exposure to noncarcinogenic and carcinogenic chemicals, respectively. The user can enter measured or predicted environmental media concentrations from the graphic interface and can simulate different exposure scenarios by selecting the appropriate pathways and modifying the exposure parameters. The database used by PESRAD-BASELINE includes dose conversion factors and slope factors for radionuclides and toxicity information and properties for chemicals. The user can modify the database for use in the calculation. Sensitivity analysis can be performed while running the computer code to examine the influence of the input parameters. Use of RESRAD-BASELINE for risk analysis is easy, fast, and cost-saving. Furthermore, it ensures in consistency in methodology for both radiological and chemical risk analyses

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

Uncertainty Analysis on the Health Risk Caused by a Radiological Terror

International Nuclear Information System (INIS)

Jeong, Hyojoon; Hwang, Wontae; Kim, Eunhan; Han, Moonhee

2010-01-01

Atmospheric dispersion modeling and uncertainty analysis were carried out support the decision making in case of radiological emergency events. The risk caused by inhalation is highly dependent on air concentrations for radionuclides, therefore air monitoring and dispersion modeling have to be performed carefully to reduce the uncertainty of the health risk assessment for the public. When an intentional release of radioactive materials occurs in an urban area, air quality for radioactive materials in the environment is of great importance to take action for countermeasures and environmental risk assessments. Atmospheric modeling is part of the decision making tasks and that it is particularly important for emergency managers as they often need to take actions quickly on very inadequate information. In this study, we assume an 137 Cs explosion of 50 TBq using RDDs in the metropolitan area of Soul, South Korea. California Puff Model is used to calculate an atmospheric dispersion and transport for 137 Cs, and environmental risk analysis is performed using the Monte Carlo method

Determining procedures for simulation-based training in radiology: a nationwide needs assessment.

Science.gov (United States)

Nayahangan, Leizl Joy; Nielsen, Kristina Rue; Albrecht-Beste, Elisabeth; Bachmann Nielsen, Michael; Paltved, Charlotte; Lindorff-Larsen, Karen Gilboe; Nielsen, Bjørn Ulrik; Konge, Lars

2018-01-09

New training modalities such as simulation are widely accepted in radiology; however, development of effective simulation-based training programs is challenging. They are often unstructured and based on convenience or coincidence. The study objective was to perform a nationwide needs assessment to identify and prioritize technical procedures that should be included in a simulation-based curriculum. A needs assessment using the Delphi method was completed among 91 key leaders in radiology. Round 1 identified technical procedures that radiologists should learn. Round 2 explored frequency of procedure, number of radiologists performing the procedure, risk and/or discomfort for patients, and feasibility for simulation. Round 3 was elimination and prioritization of procedures. Response rates were 67 %, 70 % and 66 %, respectively. In Round 1, 22 technical procedures were included. Round 2 resulted in pre-prioritization of procedures. In round 3, 13 procedures were included in the final prioritized list. The three highly prioritized procedures were ultrasound-guided (US) histological biopsy and fine-needle aspiration, US-guided needle puncture and catheter drainage, and basic abdominal ultrasound. A needs assessment identified and prioritized 13 technical procedures to include in a simulation-based curriculum. The list may be used as guide for development of training programs. • Simulation-based training can supplement training on patients in radiology. • Development of simulation-based training should follow a structured approach. • The CAMES Needs Assessment Formula explores needs for simulation training. • A national Delphi study identified and prioritized procedures suitable for simulation training. • The prioritized list serves as guide for development of courses in radiology.

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)

Dry run 1: an initial examination of a procedure for the post-closure radiological risk assessment of an underground disposal facility for radioactive waste

International Nuclear Information System (INIS)

Thompson, B.G.J.; Broyd, T.W.

1986-02-01

A probabilistic risk analysis is demonstrated for a single groundwater release scenario from a repository for intermediate level wastes at a depth of about 150 metres under Harwell. This is the first stage development of an overall methodology which will eventually treat combinations of risks due to multiple release scenarios with parameter values whose uncertainty varies with time. It is shown that upper bound estimates of risk are unlikely to be useful and that the approach to radiological risk assessment based upon 'best estimates' is difficult to justify. Consequently, a full probabilistic risk analysis is necessary although further development of statistical sampling and data acquisition techniques and also of methods for the generation and analysis of site evolution scenarios, is necessary. (author)

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)

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)

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

Request for information about radiological risks in the health area. A cross-cultural study

International Nuclear Information System (INIS)

Prades, A.; Martinez-Arias, R.; Arranz, L.; Macias, M.T.

2000-01-01

This paper will present some of the key findings of a comparative Latin-American study on radiological risk perception in the health area. The project used a survey method to examine the social demands for information about radiological risks with regard to diagnostic and therapeutic applications. The following topics will be analysed: 1) The role of information as a means for feeling safe; 2) who should inform the public on radiological risks; and 3) what type of information the public would like to receive. A questionnaire was distributed to outpatient samples from ten countries: Argentine, Brazil, Colombia, Cuba, Ecuador, Mexico, Panama, Peru, Uruguay, and Spain, thanks to the collaboration of the different National Radioprotection Societies of the above mentionned countries, and of other concerned professionals (in case they didn't had any association at the time). Correspondence analysis and other techniques of optimal scaling will be used. The paper will discuss the main cross-cultural differences with regard to social demand for information about radiological risks. Our findings may have relevant implications for radiological risks communication programs. (author)

Request for information about radiological risks in the health area. A cross-cultural study

Energy Technology Data Exchange (ETDEWEB)

Prades, A. [Ciemat, Madrid (Spain); Martinez-Arias, R. [Universidad Complutense, Madrid (Spain); Arranz, L. [Hospital Ramon y Cajal, Madrid (Spain); Macias, M.T. [CSIC, Madrid (Spain)

2000-05-01

This paper will present some of the key findings of a comparative Latin-American study on radiological risk perception in the health area. The project used a survey method to examine the social demands for information about radiological risks with regard to diagnostic and therapeutic applications. The following topics will be analysed: 1) The role of information as a means for feeling safe; 2) who should inform the public on radiological risks; and 3) what type of information the public would like to receive. A questionnaire was distributed to outpatient samples from ten countries: Argentine, Brazil, Colombia, Cuba, Ecuador, Mexico, Panama, Peru, Uruguay, and Spain, thanks to the collaboration of the different National Radioprotection Societies of the above mentionned countries, and of other concerned professionals (in case they didn't had any association at the time). Correspondence analysis and other techniques of optimal scaling will be used. The paper will discuss the main cross-cultural differences with regard to social demand for information about radiological risks. Our findings may have relevant implications for radiological risks communication programs. (author)

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 ...

Contribution o the assessment of the environmental risk associated with uranium releases in the Ritord drainage basin

International Nuclear Information System (INIS)

Beaugelin-Seiller, K.; Garnier-Laplace, J.; Gilbin, R.; Della-Vedova, C.

2008-01-01

This document reports the application to aquatic environments and more particularly to the case of a drainage basin of methods of assessment of the environmental risk presented in another report. The objective is to determine the environmental risk related to releases of uranium from ancient mining sites. The method is applied to available data to diagnose a possible chemical and/or radiological risk due to these releases. Should the occasion occurs, probabilistic approaches are used to refine the assessment of the possible risk identified by the screening. After a presentation of the context, the different screening steps are reported: methodology (exposure analysis, effect analysis, and risk characterization), deterministic characterization of the chronic radiological risk, deterministic characterization of the chronic chemical risk. The next part reports the probabilistic assessment of the chemical or radiological risk. In conclusion, the authors indicate actions to be performed to better analyse exposures, and desirable actions to better analyse effects

Pregnancy and radiation risks in radiology: users' knowledge at the University Hospital of Yopougon (Abidjan, Cote d'Ivoire)

International Nuclear Information System (INIS)

Kouame, N.; Ngoan-Domoua, A.M.; Setcheou, A.; Nezou, B.J.P.; Konan, K.D.; N'Gbesso, R.D.; Keita, A.K.

2012-01-01

Objectives: to assess the knowledge of users and health professionals about the risks of irradiation of the pregnant woman in the course of radiological examinations and the application of rules of radiation protection to pregnant women by X-ray users. Materials and Methods: our prospective study, conducted at the University Hospital of Yopougon, lasted 6 months. We interviewed 60 women who were pregnant or likely to be, 30 non-radiologist prescribing physicians, 29 medical imaging technicians and 21 health care aides on radiation risk and protective measures for pregnant women before and during the implementation of a radiological examination using X-rays. Results: 73.7% of prescribing physicians have no knowledge of radiation protection in women who are pregnant or of childbearing age. 93.1% of patients who are pregnant or of childbearing age were not aware of X-rays in diagnostic radiology and the harm they pose to a pregnant or potentially pregnant woman. 80% of radiology manipulators do not respect the basic rules of radiation protection. Conclusion: greater awareness of the users of X-ray radiation risks in pregnancy or women likely to be pregnant is required at the University Hospital of Yopougon. (authors)

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

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)

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

Radiological impact of the Argentine Nuclear Programme

International Nuclear Information System (INIS)

Gonzalez, A.J.

1983-01-01

An assessment is made of the radiological impact resulting from the activities carried out so far under the Argentine Nuclear Programme, together with a prediction of the impact which could result from the future activities planned under that Programme. The average individual risks and the radiological detriment due to the various activities are determined in terms of the average individual effective dose equivalents and the collective effective dose equivalent commitments. The assessments cover exposures of occupationally exposed workers and the public. The data obtained indicate that both the risks and the resultant detriment are reasonably comparable with those derived from other similar programmes. Moreover, they clearly indicate that the radiological impact of the Programme is tending to decrease with time so that it can be assumed that the radiological impact per unit of practice will be even lower in future. (author)

The social and cultural construction of radiological risk: a case study

International Nuclear Information System (INIS)

Van Nuffelen, D.

1996-01-01

Man, society or culture, considered as objects, cannot be measured in the same way as one would measure gravity or a hyperbola. In these conditions, how can one isolate the socio-anthropological aspects from the overall perception of radiological risks, thus the nuclear question? This paper deals with an empirical study derived from some fundamental research conducted in order to explain how different social actors conceive the nuclear question by means of different social construction of reality. It fits into the sociological scheme of knowledge posing a set of methodological and theoretical questions that have as the object the study of the social determinants of knowledge related to the nuclear question. The present survey, carried out in Belgian agricultural workers, makes clear how such determinants interact to form one social construction of the radiological risk. It allows us to presume that the perception of the radiological risks cannot be reduced to some laypeople's measurable psychic (mis)perceptions. (author)

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.

Federal Radiological Monitoring and Assessment Center (FRMAC) overview of FRMAC operations

International Nuclear Information System (INIS)

1996-02-01

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 (FRERP). This cooperative effort will assure the designated Lead Federal Agency (LFA) and the state(s) 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 the Federal Radiological Monitoring and Assessment Center (FRMAC) Operations 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. These off-site areas may include one or more affected states

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...

Methodology used by the spanish nuclear regulatory body in the radiological impact assessment

International Nuclear Information System (INIS)

Diaz de la Cruz, F.

1979-01-01

The radiological risk assessment derived from the operation of a nuclear power plant is done in Spain with methods taken basically from the U.S.N.R.C. regulatory guides. This report presents the way followed by the Spanish Regulatory Body in order to arrive to an official decision on the acceptability of a nuclear plant in the different steps of the licensing. (author)

Radiological Risk Assessment for King County Wastewater Treatment Division

Energy Technology Data Exchange (ETDEWEB)

Strom, Daniel J.

2005-08-05

Staff of 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 the combined sanitary and storm sewer system in King County, Washington. 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 (National Council on Radiation Protection and Measurements (NCRP) 2001). Radioactive material also could come from deliberate introduction or dispersion of radioactive material into the environment, including waterways and water supply systems. This document develops plausible and/or likely scenarios, including the identification of likely radioactive materials and quantities of those radioactive materials to be involved. These include 60Co, 90Sr, 137Cs, 192Ir, 226Ra, plutonium, and 241Am. Two broad categories of scenarios are considered. The first category includes events that may be suspected from the outset, such as an explosion of a "dirty bomb" in downtown Seattle. The explosion would most likely be heard, but the type of explosion (e.g., sewer methane gas or RDD) may not be immediately known. Emergency first responders must be able to quickly detect the radioisotopes previously listed, assess the situation, and deploy a response to contain and mitigate (if possible) detrimental effects resulting from the incident. In such scenarios, advance notice of about an hour or two might be available before any contaminated wastewater reaches a treatment plant. The second category includes events that could go initially undetected by emergency personnel. Examples of such a scenario would be the inadvertent or surreptitious introduction of radioactive material into the sewer system. Intact rogue radioactive sources from industrial radiography devices, well-logging apparatus, or

The Emergency Radiological Monitoring and Analysis Division of the United States Federal Radiological Monitoring and Assessment Center

International Nuclear Information System (INIS)

Thome, D.J.

2000-01-01

The U.S. Federal Radiological Emergency Response Plan (FRERP) provides the framework for integrating the various Federal agencies responding to a major radiological emergency. The FRERP authorises the creation of the Federal Radiological Monitoring and Assessment Center (FRMAC), which is established to co-ordinate 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 co-ordinating 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; 6. Integrated program of 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 Monitoring and Analysis Division and the content and preparation of the manual. (author)

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.

L-061: EPR--First responders: Risk and Protection radiological emergency

International Nuclear Information System (INIS)

2011-01-01

This conference is about the basic risks, protection and the consequences in a radiological emergency. The first responders have to know the deterministic and stochastic effects in the health as well as the cancer risk due of the high radioactive doses exposure

Contribution of the french society of radiological protection to the current reflections on the possible improvement of the radiological risk management system

International Nuclear Information System (INIS)

Lecomte, J.F.; Schieber, C.

2000-01-01

Following the invitation by IRPA to comment the article by Prof. R. Clarke entitled 'Control of Low Level Radiation Exposures: Time for a Change?', the Board of the French Radiological Protection Society (SFRP) has decided to set up a specific Working Group. This Group consists of some twenty members representing the stakeholders involved in radiological protection in France. Its goal is, starting from an analysis of R. Clarke's text, to formulate questions and proposals to assist ICRP in making its radiological protection system more understandable and more efficient. The aim of this review is not to restart from scratch but to consolidate and improve the existing system. The Working Group has therefore focused its thoughts on the following four points: 1. The basis of the radiological risk management system. In the absence of scientific certainty as to the effects of low doses of radiation, a prudent attitude has been adopted as to the manner of managing the radiological risk, based on the hypothesis that the dose-effect relationship is linear with no threshold. The Group discusses this basic assumption and its implications on the elaboration of the objectives of the radiological risk management system. 2. Exposure situations. Exposure situations are multifarious and the existing system divides them into categories for management purpose (e.g. practice/intervention; natural/artificial; medical/public/occupational; actual exposure/potential exposure; etc.). Some of these divisions are pertinent but some are less so and the Group examines if another way of conceptualising exposures situations could be more efficient. 3. Risk management indicators and tools. The radiological protection system provides the professionals with a series of indicators and tools, enabling them to manage exposure situations (dose, dose limit, dose constraint, individual dose, collective dose, investigation level, action level, interventional level, exemption level, clearance level

Status of radiation protection in interventional radiology. Assessment of inspections in 2009 by the ASN

International Nuclear Information System (INIS)

2011-01-01

This report first describes the organization of inspections performed in health institutions, indicates the inspected establishments, the types of fixed installations in interventional radiology, the use of imagery in the operating theatre, and discusses the regulatory arrangements applicable to interventional radiology (in the Public Health Code, in the Labour Code). Then, the report discusses the results of inspections regarding radiation protection in interventional radiology: application of public health code arrangements (justification, patient training in radiation protection, radiological procedures and protocols, patient dosimetry monitoring), application of Labour Code arrangements (designation of the person with expertise in radiation protection, risk assessment and delimitation of monitored and controlled areas, workstation analysis, workers' training in radiation protection, individual protection equipment, workers' dosimetric monitoring, workers' medical monitoring, radiation protection technical controls), significant events, radiation protection in operating theatre. Propositions are stated regarding the differences noticed within or between the health establishments, the methodological and organisational difficulties faced by persons with expertise in radiation protection (PCR), the need of an interdisciplinary team

Research and development in radiological protection

International Nuclear Information System (INIS)

Butragueno, J. L.; Villota, C.; Gutierrez, C.; Rodriguez, A.

2004-01-01

The objective of Radiological Protection is to guarantee that neither people, be they workers or members of the public, or the environment are exposed to radiological risks considered by society to be unacceptable. Among the various resources available to meet this objective is Research and Development (R and D), which is carried out in three areas: I. Radiological protection of persons: (a) knowledge of the biological effects of radiations, in order to determine the relationship that exists between radiation exposure dose and its effects on health; (b) the development of new personal dosimetry techniques in order to adapt to new situations, instrumental techniques and information management technologies allowing for better assessment of exposure dose; and (c) development of the principle of radiological protection optimisation (ALARA), which has been set up internationally as the fundamental principle on which radiological protection interventions are based. II. Assessment of environmental radiological impact, the objective of which is to assess the nature and magnitude of situations of exposure to ionising radiations as a result of the controlled or uncontrolled release of radioactive material to the environment, and III.Reduction of the radiological impact of radioactive wastes, the objective of which is to develop radioactive material and waste management techniques suitable for each situation, in order to reduce the risks associated with their definitive management or their release to the environment. Briefly described below are the strategic lines of R and D of the CSN, the Electricity Industry, Ciemat and Enresa in the aforementioned areas. (Author)

Quantitative evaluation of risks for individuals in diagnostic radiology

Energy Technology Data Exchange (ETDEWEB)

Iinuma, T A; Tateno, Y; Hashizume, T [National Inst. of Radiological Sciences, Chiba (Japan)

1980-05-01

A method to estimate quantitatively risks of individual patients due to exposure to diagnostic radiation (carcinogenetic and genetic effects of radiation) was proposed on the basis of ICRP-26. Carcinogenetic effect of radiation was calculated by multiplying mean dose equivalent for each organ per each radiological examination by shortening of average life-expectancy which was calculated from incidence of fetal carcinoma of each organ, latent period of carcinoma, and incidence period of carcinoma. Genetic effect of radiation was calculated by multiplying mean dose equivalent for gonad per each radiological examination by incidence of genetically severe radiation damages due to parent's exposure and child expectancy rate. Three examples were shown on calculations of risks in the photofluorographic examinations of the stomach and chest, and mammography. The same method of calculation could be applied to the in-vivo nuclear medicine examinations. Further investigation was required to calculate the risks quantitatively for various types of diagnostic procedures using radiation.

Quantitative evaluation of risks for individuals in diagnostic radiology

International Nuclear Information System (INIS)

Iinuma, T.A.; Tateno, Yukio; Hashizume, Tadashi

1980-01-01

A method to estimate quantitatively risks of individual patients due to exposure to diagnostic radiation (carcinogenetic and genetic effects of radiation) was proposed on the basis of ICRP-26. Carcinogenetic effect of radiation was calculated by multiplying mean dose equivalent for each organ per each radiological examination by shortening of average life-expectancy which was calculated from incidence of fetal carcinoma of each organ, latent period of carcinoma, and incidence period of carcinoma. Genetic effect of radiation was calculated by multiplying mean dose equivalent for gonad per each radiological examination by incidence of genetically severe radiation damages due to parent's exposure and child expectancy rate. Three examples were shown on calculations of risks in the photofluorographic examinations of the stomach and chest, and mammography. The same method of calculation could be applied to the in-vivo nuclear medicine examinations. Further investigation was required to calculate the risks quantitatively for various types of diagnostic procedures using radiation. (Tsunoda, M.)

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.

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.

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.

Federal Radiological Monitoring and Assessment Center (FRMAC): Overview of FRMAC operations

International Nuclear Information System (INIS)

1993-09-01

The purpose of this Management Overview of the Federal Radiological Monitoring and Assessment Center (FRMAC) is to explain the federal preparation for a radiological accident and to describe the subsequent response activities which provide radiological monitoring and assessment outside the boundaries of the monitoring which support the radiological accident site. In the event of a radiological accident, federal agencies with various statutory responsibilities have agreed to coordinate their efforts at the accident scene under the umbrella of the Federal Radiological Emergency Response Plan (FRERP). This cooperative effort will assure the state(s) and the Lead Federal Agency (LFA) that all federal technical assistance is fully supporting their efforts to protect the public and will provide these monitoring results in a working data center for immediate use by the state(s) and LFA decision makers. The federal agencies do not relinquish their statutory responsibilities. However, the mandated federal cooperation ensures that each agency can obtain the data critical to its specific responsibility

Lifetime attributable risk for cancer from occupational radiation exposure among radiologic technologists

Energy Technology Data Exchange (ETDEWEB)

Moon, Eun Kyeong; Lee, Won Jin [Dept. of Preventive Medicine, Korea University College of Medicine, Seoul (Korea, Republic of)

2016-12-15

Medical radiation workers were among the earliest occupational groups exposed to external ionizing radiation due to their administration of a range of medical diagnostic procedures. Ionizing radiation is a confirmed human carcinogen for most organ sites. This study, therefore, was aimed to estimate lifetime cancer risk from occupational exposure among radiologic technologists that has been recruited in 2012-2013. Our findings showed a small increased cancer risk in radiologic technologists from their occupational radiation exposure in Korea. However, continuous dose monitoring and strict regulation on occupational safety at the government level should be emphasized to prevent any additional health hazards from occupational radiation exposure. Our findings showed a small increased cancer risk in radiologic technologists from their occupational radiation exposure in Korea. However, continuous dose monitoring and strict regulation on occupational safety at the government level should be emphasized to prevent any additional health hazards from occupational radiation exposure.

Lifetime attributable risk for cancer from occupational radiation exposure among radiologic technologists

International Nuclear Information System (INIS)

Moon, Eun Kyeong; Lee, Won Jin

2016-01-01

Medical radiation workers were among the earliest occupational groups exposed to external ionizing radiation due to their administration of a range of medical diagnostic procedures. Ionizing radiation is a confirmed human carcinogen for most organ sites. This study, therefore, was aimed to estimate lifetime cancer risk from occupational exposure among radiologic technologists that has been recruited in 2012-2013. Our findings showed a small increased cancer risk in radiologic technologists from their occupational radiation exposure in Korea. However, continuous dose monitoring and strict regulation on occupational safety at the government level should be emphasized to prevent any additional health hazards from occupational radiation exposure. Our findings showed a small increased cancer risk in radiologic technologists from their occupational radiation exposure in Korea. However, continuous dose monitoring and strict regulation on occupational safety at the government level should be emphasized to prevent any additional health hazards from occupational radiation exposure.

Probabilistic risk assessment of earthquakes at the Rocky Flats Plant and subsequent upgrade to reduce risk

International Nuclear Information System (INIS)

Day, S.A.

1989-01-01

An analysis to determine the risk associated with earthquakes at the Rocky Flats Plant was performed. Seismic analyses and structural evaluations were used to postulate building and equipment damage and radiological releases to the environment from various magnitudes of earthquakes. Dispersion modeling and dose assessment to the public were then calculated. The frequency of occurrence of various magnitudes of earthquakes were determined from the Department of Energy natural Phenomena Hazards Modeling Project. Risk to the public was probabilistically assessed for each magnitude of earthquake and for overall seismic risk. Based on the results of this Probabilistic Risk Assessment and a cost/benefit analysis, seismic upgrades are being implemented for several plutonium-handling facilities for the purpose of risk reduction

Status report on the EPRI fuel cycle accident risk assessment

International Nuclear Information System (INIS)

Erdmann, R.C.; Fullwood, R.R.; Garcia, A.A.; Mendoza, Z.T.; Ritzman, R.L.; Stevens, C.A.

1979-07-01

This report summarizes and extends the work reported in five unpublished draft reports: the accidental radiological risk of reprocessing spent fuel, mixed oxide fuel fabrication, the transportation of materials within the fuel cycle, and the disposal of nuclear wastes, and the routine atmospheric radiological risk of mining and milling uranium-bearing ore. Results show that the total risk contribution of the fuel cycle is only about 1% of the accident risk of the power plant and hence, with little error, the accident risk of nuclear electric power is that of the power plant itself. The power plant risk, assuming a very large usage of nuclear power by the year 2005, is only about 0.5% of the radiological risk of natural background. This work aims at a realistic assessment of the process hazards, the effectiveness of confinement and mitigation systems and procedures, and the associated likelihoods and estimated errors. The primary probabilistic estimation tool is fault tree analysis with the release source terms calculated using physical--chemical processes. Doses and health effects are calculated with the CRAC code. No evacuation or mitigation is considered: source terms may be conservative through the assumption of high fuel burnup (40,000 MWd/T) and short cooling (90 to 150 d); HEPA filter efficiencies are derived from experiments

Toward raising the higher level of radiological nursing

International Nuclear Information System (INIS)

Kusama, Tomoko; Ban, Nobuhiko; Ono, Koji

2013-01-01

The role and purpose of nursing in the radiological field are discussed with essentials of radiological nursing for raising its higher level and needed fundamental education. The discussion is from the thought that, at Fukushima Nuclear Power Plant Accident (Mar. 2011), general medical staff including nurses are rather insufficient of radiological knowledge like the exposure, radiation effect and risk. In the medical radiological field, nurses are expected to play roles of arranging the circumstance for patient's ease like explanation about health effect/risk, appropriate nursing of them after radiological diagnosis, radiation protection of nurses themselves, and of environment. At such an emergency as the Accident, care for the acutely exposed victims, their decontamination and responding to patient's concern are necessary. At the later phase, also needed are nursing of victims undergoing health management done by authorities and of radiological workers concerned as well as the third item above. Therefore, fundamentals of radiological knowledge such as physics, exposure, health effects, protection, contamination, legal rules and risk communication are required in the education of nurses. Otherwise, this education can be conducted as a part of safety security and physical assessment. The Accident also gives us the importance of radiological risk communication with its victims. (T.T.)

Medicine and ionizing rays: a help sheet in analysing risks in intra-oral dental radiology and applicable texts

International Nuclear Information System (INIS)

Gauron, C.

2009-01-01

This document proposes a synthesis of useful knowledge for radioprotection in the case of intra-oral dental radiology. In the first part, several aspects are considered: the concerned personnel, the course of treatment procedures, the hazards, the identification of the risk associated with ionizing radiation, the risk assessment and the determination of exposure levels, the strategy to control the risks (reduction of risks, technical measures concerning the installation or the personnel, teaching and information, prevention and medical monitoring), and risk control assessment. A second part indicates the various applicable legal and regulatory texts (European directives, institutions in charge of radioprotection, general arrangements applicable to workers and patients, and regulatory texts concerning worker protection or patient protection against ionizing radiations)

Assessment of the radiological impact of the transport of radioactive materials

International Nuclear Information System (INIS)

1986-12-01

In order to facilitate the assessment of the radiological impact of transport, and to guide the collection of data for future assessments, the IAEA convened a technical committee (The Technical Committee on the Assessment of the Radiological Impact from the Transport of Radioactive Materials; TC-556) in Vienna, Austria on 21-25 October 1985. The Terms of Reference called for this committee ''to collect and assess data on the radiation exposure of workers and the public during the transport of radioactive material, and to develop a summary statement, reflecting current practice and current state of knowledge, on the radiological impact of transport.'' This technical document provides the summary statement developed by TC-556. The statement should be viewed as an interim assessment since it utilized only data then available, or made available, to the committee. This document consists of three Sections: Section I - Background Information to the Summary Statement (prepared by the Secretariat); Section II - The Summary Statement on the Radiological Impact of the Transport of Radioactive Materials (developed by TC-556); and Section III - Recommendations for Future Assessments (a summary of statements and conclusions provided in the TC-556 Chairman's Report)

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.

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.

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)

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

Application of probabilistic risk assessment to reprocessing

International Nuclear Information System (INIS)

Perkins, W.C.

1984-01-01

The Savannah River Laboratory uses probabilistic methods of risk assessment in safety analyses of reprocessing facilities at the Savannah River Plant. This method uses both the probability of an accident and its consequence to calculate the risks from radiological, chemical, and industrial hazards. The three principal steps in such an assesment are identification of accidents, calculation of frequencies, and consequence quantification. The tools used at SRL include several databanks, logic tree methods, and computer-assisted methods for calculating both frequencies and consequences. 5 figures

ICPP radiological and toxicological sabotage analysis

International Nuclear Information System (INIS)

Kubiak, V.R.; Mortensen, F.G.

1995-01-01

In June of 1993, the Department of Energy (DOE) issued Notice 5630.3A, open-quotes Protection of Departmental Facilities Against Radiological and Toxicological Sabotage,close quotes which states that all significant radiological and toxicological hazards at Department facilities must be examined for potential sabotage. This analysis has been completed at the Idaho Chemical Processing Plant (ICPP). The ICPP radiological and toxicological hazards include spent government and commercial fuels, Special Nuclear Materials (SNM), high-level liquid wastes, high-level solid wastes, and process and decontamination chemicals. The analysis effort included identification and assessment of quantities of hazardous materials present at the facility; identification and ranking of hazardous material targets; development of worst case scenarios detailing possible sabotage actions and hazard releases; performance of vulnerability assessments using table top and computer methodologies on credible threat targets; evaluation of potential risks to the public, workers, and the environment; evaluation of sabotage risk reduction options; and selection of cost effective prevention and mitigation options

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

The way to inform the general public about radiological risks

International Nuclear Information System (INIS)

Artus, J.C.

2002-01-01

It is a lawfully necessity that the general public will be informed about matters of radiological risks. For that practitioners have to receive an appropriate knowledge about risk parameters, so the effective dose. Moreover they must do their utmost to give information to their patients, in a context of false ideas and often exaggerated prejudices. (author)

Support to triage and public risk perception considering long-term response to a Cs-137 radiological dispersive device scenario.

Science.gov (United States)

Andrade, Cristiane Ps; Souza, Cláudio J; Camerini, Eduardo Sn; Alves, Isabela S; Vital, Hélio C; Healy, Matthew Jf; Ramos De Andrade, Edson

2018-01-01

A radiological dispersive device (RDD) spreads radioactive material, complicates the treatment of physical injuries, raises cancer risk, and induces disproportionate fear. Simulating such an event enables more effective and efficient utilization of the triage and treatment resources of staff, facilities, and space. Fast simulation can give detail on events in progress or future events. The resources for triage and treatment of contaminated trauma victims can differ for pure exposure individuals, while discouraging the "worried well" from presenting in the crisis phase by media announcement would relieve pressure on hospital facilities. The proposed methodology integrates capabilities from different platforms in a convergent way composed of three phases: (a) scenario simulation, (b) data generation, and (c) risk assessment for triage focused on follow-up epidemiological assessment. Simulations typically indicate that most of the affected population does not require immediate medical assistance. Medical triage for the few severely injured and the radiological triage to diminish the contamination with radioactivity will always be the priority. For this study, however, higher priorities should be given to individuals from radiological "warm" and "hot" zones as required by risk criteria. The proposed methodology could thus help to (a) filter and reduce the number of individuals to be attended, (b) optimize the prioritization of medical care, (c) reduce or prepare for future costs, (d) effectively locate the operational triage site to avoid possible contamination on the main facility, and (e) provide the scientific data needed to develop an adequate approach to risk and its proper communication.

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.

Patient exposure in paediatric radiology

International Nuclear Information System (INIS)

Iacob, O.; Diaconescu, C.; Isac, R.

2002-01-01

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 was to assess, in terms of effective dose, the magnitude of paediatric patient exposure during conventional X-ray examinations, selected for their high frequency or their relatively high doses delivered to patient

Radiological health risks from accidents during transportation of spent nuclear fuels

International Nuclear Information System (INIS)

Chen, S.Y.; Yuan, Y.C.

1988-01-01

Potential radiological health risks from severe accident scenarios during the transportation of spent nuclear fuels are estimated. These extremely low probability, but potentially credible, scenarios are characterized by the U.S. Nuclear Regulatory Commission's Modal Study in terms of the maximum credible structural responses and/or the maximum credible cask temperature responses. In some accident scenarios, the spent nuclear fuel casks are assumed to be breached, resulting in the release of radioactivity to the atmosphere. Models have been developed to estimate radiological health consequences, including potential short-term exposures and health effects to individuals and potential long-term environmental dose commitments and health effects to the population. The population risks are calculated using state-level data, and the resulting overall health risks are compared for several levels of cleanup effort to determine the relative effects on long-term risks to the population in the event of an accident. 4 refs., 3 figs., 3 tabs

HTGR containment design options: an application of probabilistic risk assessment

International Nuclear Information System (INIS)

1977-08-01

Through the use of probabilistic risk assessment (PRA), it is possible to quantitatively evaluate the radiological risk associated with a given reactor design and to place such risk into perspective with alternative designs. The merits are discussed for several containment alternatives for the HTGR from the viewpoints of economics and licensability, as well as public risk. The quantification of cost savings and public risk indicates that presently acceptable public risk can be maintained and cost savings of $40 million can result from use of a vented confinement for the HTGR

Radiology and risk: an economist's perspective

International Nuclear Information System (INIS)

Mooney, G.H.

1981-01-01

This paper, is an amended version of a talk given to The British Institute of Radiology at a meeting on ''Dosimetry and Risks to Patients in Radiopharmaceutical Investigations''. It explains cost-benefit analysis (distinguishing it from cost-effectiveness analysis) and suggests various ways of trying to place a value on human life in order to use cost-benefit analysis as a practical tool of decision-making in policy areas where at least part of the benefit is to be measured in terms of lives saved. The paper suggests that it is important to decide not only who is to value life but also whose perceptions of risk of death are to be deemed relevant. A practical example in the use of life values is presented for the case of mammography in breast cancer screening. (author)

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

RISKIND: A computer program for calculating radiological consequences and health risks from transportation of spent nuclear fuel

Energy Technology Data Exchange (ETDEWEB)

Yuan, Y.C. [Square Y Consultants, Orchard Park, NY (US); Chen, S.Y.; Biwer, B.M.; LePoire, D.J. [Argonne National Lab., IL (US)

1995-11-01

This report presents the technical details of RISKIND, a computer code designed to estimate potential radiological consequences and health risks to individuals and the collective population from exposures associated with the transportation of spent nuclear fuel. RISKIND is a user-friendly, interactive program that can be run on an IBM or equivalent personal computer under the Windows{trademark} environment. Several models are included in RISKIND that have been tailored to calculate the exposure to individuals under various incident-free and accident conditions. The incident-free models assess exposures from both gamma and neutron radiation and can account for different cask designs. The accident models include accidental release, atmospheric transport, and the environmental pathways of radionuclides from spent fuels; these models also assess health risks to individuals and the collective population. The models are supported by databases that are specific to spent nuclear fuels and include a radionuclide inventory and dose conversion factors. In addition, the flexibility of the models allows them to be used for assessing any accidental release involving radioactive materials. The RISKIND code allows for user-specified accident scenarios as well as receptor locations under various exposure conditions, thereby facilitating the estimation of radiological consequences and health risks for individuals. Median (50% probability) and typical worst-case (less than 5% probability of being exceeded) doses and health consequences from potential accidental releases can be calculated by constructing a cumulative dose/probability distribution curve for a complete matrix of site joint-wind-frequency data. These consequence results, together with the estimated probability of the entire spectrum of potential accidents, form a comprehensive, probabilistic risk assessment of a spent nuclear fuel transportation accident.

RISKIND: A computer program for calculating radiological consequences and health risks from transportation of spent nuclear fuel

International Nuclear Information System (INIS)

Yuan, Y.C.; Chen, S.Y.; Biwer, B.M.; LePoire, D.J.

1995-11-01

This report presents the technical details of RISKIND, a computer code designed to estimate potential radiological consequences and health risks to individuals and the collective population from exposures associated with the transportation of spent nuclear fuel. RISKIND is a user-friendly, interactive program that can be run on an IBM or equivalent personal computer under the Windows trademark environment. Several models are included in RISKIND that have been tailored to calculate the exposure to individuals under various incident-free and accident conditions. The incident-free models assess exposures from both gamma and neutron radiation and can account for different cask designs. The accident models include accidental release, atmospheric transport, and the environmental pathways of radionuclides from spent fuels; these models also assess health risks to individuals and the collective population. The models are supported by databases that are specific to spent nuclear fuels and include a radionuclide inventory and dose conversion factors. In addition, the flexibility of the models allows them to be used for assessing any accidental release involving radioactive materials. The RISKIND code allows for user-specified accident scenarios as well as receptor locations under various exposure conditions, thereby facilitating the estimation of radiological consequences and health risks for individuals. Median (50% probability) and typical worst-case (less than 5% probability of being exceeded) doses and health consequences from potential accidental releases can be calculated by constructing a cumulative dose/probability distribution curve for a complete matrix of site joint-wind-frequency data. These consequence results, together with the estimated probability of the entire spectrum of potential accidents, form a comprehensive, probabilistic risk assessment of a spent nuclear fuel transportation accident

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)

Soil radioactivity levels, radiological maps and risk assessment for the state of Kuwait.

Science.gov (United States)

Alazemi, N; Bajoga, A D; Bradley, D A; Regan, P H; Shams, H

2016-07-01

An evaluation of the radioactivity levels associated with naturally occurring radioactive materials has been undertaken as part of a systematic study to provide a surface radiological map of the State of Kuwait. Soil samples from across Kuwait were collected, measured and analysed in the current work. These evaluations provided soil activity concentration levels for primordial radionuclides, specifically members of the (238)U and (232)Th decay chains and (40)K which. The (238)U and (232)Th chain radionuclides and (40)K activity concentration values ranged between 5.9 ↔ 32.3, 3.5 ↔ 27.3, and 74 ↔ 698 Bq/kg respectively. The evaluated average specific activity concentrations of (238)U, (232)Th and (40)K across all of the soil samples have mean values of 18, 15 and 385 Bq/kg respectively, all falling below the worldwide mean values of 35, 40 and 400 Bq/kg respectively. The radiological risk factors are associated with a mean of 33.16 ± 2.46 nG/h and 68.5 ± 5.09 Bq/kg for the external dose rate and Radium equivalent respectively. The measured annual dose rates for all samples gives rise to a mean value of 40.8 ± 3.0 μSv/y while the internal and internal hazard indices have been found to be 0.23 ± 0.02 and 0.19 ± 0.01 respectively. Copyright © 2016 Elsevier Ltd. All rights reserved.

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)

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.

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)

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

Radiological Risk Assessments for Occupational Exposure at Fuel Fabrication Facility in AlTuwaitha Site Baghdad – Iraq by using RESRAD Computer Code

Science.gov (United States)

Ibrahim, Ziadoon H.; Ibrahim, S. A.; Mohammed, M. K.; Shaban, A. H.

2018-05-01

The purpose of this study is to evaluate the radiological risks for workers for one year of their activities at Fuel Fabrication Facility (FFF) so as to make the necessary protection to prevent or minimize risks resulted from these activities this site now is under the Iraqi decommissioning program (40). Soil samples surface and subsurface were collected from different positions of this facility and analyzed by gamma rays spectroscopy technique High Purity Germanium detector (HPGe) was used. It was found out admixture of radioactive isotopes (232Th 40K 238U 235U137Cs) according to the laboratory results the highest values were (975758) for 238U (21203) for 235U (218) for 232Th (4046) for 40K and (129) for 137Cs in (Bqkg1) unit. The annual total radiation dose and risks were estimated by using RESRAD (onsite) 70 computer code. The highest total radiation dose was (5617μSv/year) in area that represented by soil sample (S7) and the radiological risks morbidity and mortality (118E02 8661E03) respectively in the same area

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.

Application of improved topsis method to comprehensive assessment of radiological environmental quality

International Nuclear Information System (INIS)

Shi Dongsheng; Di Yuming; Zhou Chunlin

2007-01-01

TOPSIS is a method for multiobjective decision-making, which can be applied to comprehensive assessment of radiological environmental quality. This paper introduces the principle of TOPSIS method and sets up the model of improved TOPSIS method, discusses the application of improved TOPSIS method to comprehensive assessment of radiological environmental quality. This method sufficiently makes use of the information of the optimal matrix. Analysis of practical examples using MATLAB program shows that it is objectively reasonable and feasible to comprehensively assess radiological environmental quality by improved TOPSIS method. This paper also provides the result of optimum number of sites and compares it with optimal index method based on TOPSIS method and traditional method. (authors)

Failure rate data for fusion safety and risk assessment

International Nuclear Information System (INIS)

Cadwallader, L.C.

1993-01-01

The Fusion Safety Program (FSP) at the Idaho National Engineering Laboratory (INEL) conducts safety research in materials, chemical reactions, safety analysis, risk assessment, and in component research and development to support existing magnetic fusion experiments and also to promote safety in the design of future experiments. One of the areas of safety research is applying probabilistic risk assessment (PRA) methods to fusion experiments. To apply PRA, we need a fusion-relevant radiological dose code and a component failure rate data base. This paper describes the FSP effort to develop a failure rate data base for fusion-specific components

Assessment of radiological risks at the ATLAS experiment. Author-review of the Thesis

International Nuclear Information System (INIS)

Zajacova, Z.

2009-01-01

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)

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)

Research progress of non-human species radiological impact and assessment

International Nuclear Information System (INIS)

Bai Xiaoping; Zhu Hao; Mao Yawei; Zheng Wei; Du Hongyan

2014-01-01

In recent years, with the development of radiological protection conception and the improvement of requirement about non-human species protection, much more attention has been paid gradually to biota radiation impact. Research and development of non-human species protection impact and its assessment at home and abroad are introduced, then RESRAD-BIOTA and ERICA which are comparatively mature codes in the world are compared and analyzed, at last some suggestions about research and assessment work of non-human species radiological impact in the future in China are provided. (authors)

Assessment of the long-term risk of a meteorite impact on a hypothetical Canadian nuclear fuel waste disposal vault deep in plutonic rock

International Nuclear Information System (INIS)

Wuschke, D.M.; Whitaker, S.H.; Goodwin, B.W.; Rasmussen, L.R.

1995-06-01

This report describes an assessment of the long-term radiological risk to an individual of the critical group that would result from a meteorite impact on a hypothetical reference disposal vault for used fuel, located 500 m below the Earth's surface. The purpose of the assessment was to determine if this radiological risk could exceed or approach the AECB risk criterion. (author). 47 refs., 5 tabs., 6 figs

Work history and mortality risks in 90,268 US radiological technologists.

Science.gov (United States)

Liu, Jason J; Freedman, D Michal; Little, Mark P; Doody, Michele M; Alexander, Bruce H; Kitahara, Cari M; Lee, Terrence; Rajaraman, Preetha; Miller, Jeremy S; Kampa, Diane M; Simon, Steven L; Preston, Dale L; Linet, Martha S

2014-12-01

There have been few studies of work history and mortality risks in medical radiation workers. We expanded by 11 years and more outcomes our previous study of mortality risks and work history, a proxy for radiation exposure. Using Cox proportional hazards models, we estimated mortality risks according to questionnaire work history responses from 1983 to 1989 through 2008 by 90,268 US radiological technologists. We controlled for potential confounding by age, birth year, smoking history, body mass index, race and gender. There were 9566 deaths (3329 cancer and 3020 circulatory system diseases). Mortality risks increased significantly with earlier year began working for female breast (p trend=0.01) and stomach cancers (p trend=0.01), ischaemic heart (p trend=0.03) and cerebrovascular diseases (p trend=0.02). The significant trend with earlier year first worked was strongly apparent for breast cancer during baseline through 1997, but not 1998-2008. Risks were similar in the two periods for circulatory diseases. Radiological technologists working ≥5 years before 1950 had elevated mortality from breast cancer (HR=2.05, 95% CI 1.27 to 3.32), leukaemia (HR=2.57, 95% CI 0.96 to 6.68), ischaemic heart disease (HR=1.13, 95% CI 0.96 to 1.33) and cerebrovascular disease (HR=1.28, 95% CI 0.97 to 1.69). No other work history factors were consistently associated with mortality risks from specific cancers or circulatory diseases, or other conditions. Radiological technologists who began working in early periods and for more years before 1950 had increased mortality from a few cancers and some circulatory system diseases, likely reflecting higher occupational radiation exposures in the earlier years. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://group.bmj.com/group/rights-licensing/permissions.

Conventional radiology: fixed installations in medical environment

International Nuclear Information System (INIS)

2010-01-01

This document presents the different procedures, the different types of specific hazards, the analysis of risks, their assessment and the preventive methods with regard to radioprotection in the case of fixed conventional radiology equipment in medical environment. It indicates and describes the concerned personnel, the course of procedures, the hazards, the identification of the risk associated with ionizing radiation, the risk assessment and the determination of exposure levels (definition of regulated areas, personnel categories), the strategy aimed at controlling the risk (risk reduction, technical measures concerning the installation or the personnel, teaching and information, prevention, incident), the different measures of medical monitoring, the assessment of risk control, and other risks. An appendix proposes an example of workstation assessment

Dosimetry in diagnosis examinations in radiology

International Nuclear Information System (INIS)

Lisbona, Albert; Aubert, Bernard; Laffont, Sophie; Beaumont, Stephane; Catala, Alexandre; Cohard, Cecile; Cordoliani, Yves-Sebastien; Giraud, Jean-Yves; Lescrainier, Jacques; Noel, Alain; Verdun, Francis R.

2003-01-01

This document aims at helping the professionals involved in radiology when assessing the delivered doses to patients during conventional radiology examinations, in mammography and scanography. The first part recalls all the dosimetric data susceptible to characterize the X ray beam, the patient exposure and the radiological risk. The second part addresses the different types of sensors which can be used to obtain the different measurable dosimetric values. The third part presents the calculation, analytical and numerical methods. The fourth part proposes a set of sheets of data to be acquired on an installation to perform a measurement and/or a dose calculation

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

Assessment and management of cancer risks from radiological and chemical hazards

International Nuclear Information System (INIS)

1998-01-01

A Joint Working Group was established in April 1995 by the President of the Atomic Energy Control Board (AECB) and the Assistant Deputy Minister of the Health Protection Branch of Health Canada to examine the similarities, disparities and inconsistencies between the levels of risk considered acceptable for regulating ionizing radiation and those considered acceptable for regulating chemical and microbiological hazards. During the process of collecting, analysing and interpreting information, the Joint Working Group realized that its terms of reference as written presented a major difficulty because of the lack of consensus on acceptable levels of risk. Consequently it decided that the most reasonable way to proceed was to compare the risk assessment and management processes used to protect the public from radiation, chemicals and microbiological hazards. This report concentrates on the assessment and management of ionizing radiation and genotoxic chemicals (which both cause cancer by damaging the DNA in cells) and pays less attention to non-genotoxic effects and microbiological hazards. The report also examines public more than occupational exposures and exposures from man-made rather than naturally occurring agents. (author)

Ecological risk assessment for radiological and chemical contaminants at a site with historical contamination

International Nuclear Information System (INIS)

Garisto, N.C.; Janes, A.; Peters, R.

2010-01-01

An Ecological Risk Assessment was carried out for a uranium conversion facility in Ontario, located on a site with a history of contamination. The ERA assessed risk to aquatic and terrestrial biota from exposure to radionuclides and non-radionuclides in soil and groundwater associated with the site. The results indicated no undue risk to aquatic biota from radionuclides. Small potential risks were identified for terrestrial biota at limited locations associated with this industrial site. Recommendations are provided for follow-up risk-informed activities. (author)

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

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

Methodology of environmental risk assessment management

Directory of Open Access Journals (Sweden)

Saša T. Bakrač

2012-04-01

Full Text Available Successful protection of environment is mostly based on high-quality assessment of potential and present risks. Environmental risk management is a complex process which includes: identification, assessment and control of risk, namely taking measures in order to minimize the risk to an acceptable level. Environmental risk management methodology: In addition to these phases in the management of environmental risk, appropriate measures that affect the reduction of risk occurrence should be implemented: - normative and legal regulations (laws and regulations, - appropriate organizational structures in society, and - establishing quality monitoring of environment. The emphasis is placed on the application of assessment methodologies (three-model concept, as the most important aspect of successful management of environmental risk. Risk assessment methodology - European concept: The first concept of ecological risk assessment methodology is based on the so-called European model-concept. In order to better understand this ecological risk assessment methodology, two concepts - hazard and risk - are introduced. The European concept of environmental risk assessment has the following phases in its implementation: identification of hazard (danger, identification of consequences (if there is hazard, estimate of the scale of consequences, estimate of consequence probability and risk assessment (also called risk characterization. The European concept is often used to assess risk in the environment as a model for addressing the distribution of stressors along the source - path - receptor line. Risk assessment methodology - Canadian concept: The second concept of the methodology of environmental risk assessment is based on the so-called Canadian model-concept. The assessment of ecological risk includes risk arising from natural events (floods, extreme weather conditions, etc., technological processes and products, agents (chemical, biological, radiological, etc

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.

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

Implications of recent ICRP recommendations for risk assessments for radioactive waste disposal and cleanup

International Nuclear Information System (INIS)

Devgun, J.S.

1992-01-01

The International Commission on Radiological Protection (ICRP) adopted a new set of recommendations in November 1990 which were issued at ICRP Publication No. 60 in March 1991. These recommendations incorporate new radiobiological information and outline a comprehensive system of radiological protection. This paper evaluates the implications of these new recommendations vis a vis risk assessments for radioactive waste disposal and remediation of radioactively contaminated sites

Radiological Risk Assessment and Cask Materials Qualification for Disposed Sealed Radioactive Sources Transport

International Nuclear Information System (INIS)

Margeanu, C.A.; Olteanu, G.; Bujoreanu, D.

2009-01-01

The hazardous waste problem imposes to respect national and international agreed regulations regarding their transport, taking into account both for maintaining humans, goods and environment exposure under specified limits, during transport and specific additional operations, and also to reduce impact on the environment. The paper follows to estimate the radiological risk and cask materials qualification according to the design specifications for disposed sealed radioactive sources normal transport situation. The shielding analysis has been performed by using Oak Ridge National Laboratory's SCALE 5 programs package. For thermal analysis and cask materials qualification ANSYS computer code has been used. Results have been obtained under the framework of Advanced system for monitoring of hazardous waste transport on the Romanian territory Research Project which main objective consists in implementation of a complex dual system for on-line monitoring both for transport special vehicle and hazardous waste packages, with data automatic transmission to a national monitoring center

Comparison of the MARC and CRAC2 programs for assessing the radiological consequences of accidental releases of radioactive material

CERN Document Server

Hemming, C R; Charles, D; Ostmeyer, R M

1983-01-01

This report describes a comparison of the MARC (Methodology for Assessing Radiological Consequences) and CRAC2 (Calculation of Reactor Accident Consequences, version 2) computer programs for assessing the radiological consequences of accidental releases of radioactive material. A qualitative comparison has been made of the features of the constituent sub-models of the two codes, and potentially the most important differences identified. The influence of these differences has been investigated quantitatively by comparison of the predictions of the two codes in a wide variety of circumstances. Both intermediate quantities and endpoints used as a measure of risk have been compared in order to separate the variables more clearly. The results indicate that, in general, the predictions of MARC and CRAC2 are in good agreement.

Radiological assessment and management of radioactive spill in a liquid waste treatment facility - Case study

International Nuclear Information System (INIS)

Amer, H.A.; Shawky, S.; Ibrahiem, N.

2002-01-01

The radiological assessment and management of radioactive spill from liquid waste treatment facility is presented. The incident contaminated the area surrounding the treatment facility with various radionuclides, which were dispersed into the soil. A method based on the European basic safety standards was used to contain the risks associated with the contaminated site. The introduced case study proceeded up to the stage of simplified risk study, since the site is small and it was relatively easy to remove and store the contaminated soil. According to the obtained results, the removal of the upper 30-cm would be considered as appropriate remedying action to resume background level. One of the most important basic concepts of radiation protection in nuclear facilities is the continuity of monitoring radiological release to the environment. It is known that from nuclear facilities only very small amounts of radioactivity are discharged with the liquid effluents and the exhaust air into the environment. Recent studies screening the natural and artificial radionuclide in soil samples from the investigated area revealed normal background concentrations with no anomalies

Simplified risk assessment for transporting ATR spent fuel within the INEL

International Nuclear Information System (INIS)

Franklin, E.M.; Courtney, J.C.

1994-01-01

Interest in characterizing the condition of stored spent fuels has generated the need to move spent fuels to hot cell facilities within the Idaho National Engineering Laboratory (INEL). A simplified probabilistic risk assessment (SPRA) and an evaluation of the radiological consequences in the event of an accident are discussed and applied to on-site Advanced Test Reactor (AYR) spent fuel shipments. Reported accident probabilities between 10 -4 and 10 -6 and low radiological consequences, affords this, and other spent fuel characterization efforts, an additional option to move spent fuels within the INEL

The concept of radiological risk and the epidemiology of the ionizing radiation

International Nuclear Information System (INIS)

Angeles C, A.; Garcia M, T.; Benitez S, J. A.

2013-10-01

The present work has as objective to describe in general way which is the methodology to be able to propose and to determine the exhibition limits of the ionizing radiations in terms of the radiological risk. First a description of the radiological risk concept is made, considering that the concept has more than a meaning, but that technical and scientifically is a punctual concept. Starting from the understanding of the term risk and example of numeric calculation of the same one is made and next a description of the epidemiology meaning is made. The epidemiology concept is described and a brief description of three of the main epidemic methods is made: the ecological, analytic, (divided in case-control) and cohort studies. A description is made of how starting from the statistical data of cohort studies the mortality data are obtained in terms of the cause-effect relationship, being these dose-cancer like the main stochastic effect and later on starting from these data models are proposed to describe the radiological risk. As the dose levels of the considered cohorts are very high in comparison with the normal labor levels, then the cause-effect models should be extrapolated for low dose levels, once established these models are to decide the grade of acceptable risk for the activity that involves the use of ionizing radiations, starting from there and with numeric values the dose limits to recommend are established and that would be adopted by the countries or regions in terms of their social, economic and technical conditions. (Author)

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)

L-035: EPR-First Responders: Basic Risk and Protection for First Responders to a Radiological Emergency

International Nuclear Information System (INIS)

2011-01-01

There are some basic actions and self-protective actions to take in an radiological emergency. Radiation is detected with appropriate instrumentation and measuring the rate of exposure (Sv per hour) in contact with radioactive materials involved. Is important to note: Responsive to a radiological emergency, tool to identify radiological risks, radiation protection, radioactive symbol and instrumentation

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.

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

137Cs Radiological risk estimation of NSD facility at Karawang site by using RESRAD onsite application: effect of cover thickness

Science.gov (United States)

Setiawan, B.; Prihastuti, S.; Moersidik, S. S.

2018-02-01

The operational of near surface disposal facility during waste packages loading activity into the facility, or in a monitoring activity around disposal facility at Karawang area is predicted to give a radiological risk to radiation workers. The thickness of disposal facility cover system affected the number of radiological risk of workers. Due to this reason, a radiological risk estimation needs to be considered. RESRAD onsite code is applied for this purpose by analyse the individual accepted dose and radiological risk data of radiation workers. The obtained results and then are compared with radiation protection reference in accordance with national regulation. In this case, the data from the experimental result of Karawang clay as host of disposal facility such as Kd value of 137Cs was used. Results showed that the thickness of the cover layer of disposal facility affected to the radiological risk which accepted by workers in a near surface disposal facility.

Clean Slate transportation and human health risk assessment

International Nuclear Information System (INIS)

1997-02-01

Public concern regarding activities involving radioactive material generally focuses on the human health risk associated with exposure to ionizing radiation. This report describes the results of a risk analysis conducted to evaluate risk for excavation, handling, and transport of soil contaminated with transuranics at the Clean Slate sites. Transportation risks were estimated for public transport routes from the Tonopah Test Range (TTR) to the Envirocore disposal facility or to the Area 3 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS) for both radiological risk and risk due to traffic accidents. Human health risks were evaluated for occupational and radiation-related health effects to workers. This report was generated to respond to this public concern, to provide an evaluation of the risk, and to assess feasibility of transport of the contaminated soil for disposal

Cost-effectiveness and radiological risk associated with mass chest screening

International Nuclear Information System (INIS)

Stieve, F.E.

1987-01-01

This report presents in summary the cost effectiveness and radiological risks associated with mass chest tuberculosis screening in major European countries. The state of tuberculosis in west Europe, the cost effectiveness of mass screening, international standards regarding radiation doses as well as the need for quality control are addressed

Uncertainties in environmental radiological assessment models and their implications

International Nuclear Information System (INIS)

Hoffman, F.O.; Miller, C.W.

1983-01-01

Environmental radiological assessments rely heavily on the use of mathematical models. The predictions of these models are inherently uncertain because these models are inexact representations of real systems. The major sources of this uncertainty are related to biases in model formulation and parameter estimation. The best approach for estimating the actual extent of over- or underprediction is model validation, a procedure that requires testing over the range of the intended realm of model application. Other approaches discussed are the use of screening procedures, sensitivity and stochastic analyses, and model comparison. The magnitude of uncertainty in model predictions is a function of the questions asked of the model and the specific radionuclides and exposure pathways of dominant importance. Estimates are made of the relative magnitude of uncertainty for situations requiring predictions of individual and collective risks for both chronic and acute releases of radionuclides. It is concluded that models developed as research tools should be distinguished from models developed for assessment applications. Furthermore, increased model complexity does not necessarily guarantee increased accuracy. To improve the realism of assessment modeling, stochastic procedures are recommended that translate uncertain parameter estimates into a distribution of predicted values. These procedures also permit the importance of model parameters to be ranked according to their relative contribution to the overall predicted uncertainty. Although confidence in model predictions can be improved through site-specific parameter estimation and increased model validation, risk factors and internal dosimetry models will probably remain important contributors to the amount of uncertainty that is irreducible

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)

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

Risks arising during manipulation with radiologically specific products of biotechnical production

International Nuclear Information System (INIS)

Mitrovic, R.; Vukovic, D.; Vicentijevic, M.; Kljajic, R.

1998-01-01

Objective of this study was to review the risk of exposure to radiocaesium (134+137Cs), which biologically presents the most toxic radionuclide, of people engaged in the process of supervision, transport and storage of the radiologically specific products, like concentrated protein feedstuff (fish meal, powdered milk), wool, cow hide and chamois. The discussion is based on the results of a radiological-hygienic analysis of these products in the context of veterinary-sanitary control, performed in the authorized referent Laboratory for Radiation Hygiene (LABRAH) at the Scientific Institute for Veterinary Medicine of Serbia in Belgrade (Yugoslavia)

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

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

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.

Risk and dose assessment methods in gamma knife QA

International Nuclear Information System (INIS)

Banks, W.W.; Jones, E.D.; Rathbun, P.

1992-10-01

Traditional methods used in assessing risk in nuclear power plants may be inappropriate to use in assessing medical radiation risks. The typical philosophy used in assessing nuclear reactor risks is machine dominated with only secondary attention paid to the human component, and only after critical machine failure events have been identified. In assessing the risk of a misadministrative radiation dose to patients, the primary source of failures seems to stem overwhelmingly, from the actions of people and only secondarily from machine mode failures. In essence, certain medical misadministrations are dominated by human events not machine failures. Radiological medical devices such as the Leksell Gamma Knife are very simple in design, have few moving parts, and are relatively free from the risks of wear when compared with a nuclear power plant. Since there are major technical differences between a gamma knife and a nuclear power plant, one must select a particular risk assessment method which is sensitive to these system differences and tailored to the unique medical aspects of the phenomena under study. These differences also generate major shifts in the philosophy and assumptions which drive the risk assessment (Machine-centered vs Person-centered) method. We were prompted by these basic differences to develop a person-centered approach to risk assessment which would reflect these basic philosophical and technological differences, have the necessary resolution in its metrics, and be highly reliable (repeatable). The risk approach chosen by the Livermore investigative team has been called the ''Relative Risk Profile Method'' and has been described in detail by Banks and Paramore, (1983)

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.

Lessons learned from joint working group report on assessment and management of cancer risks from radiological and chemical hazards

International Nuclear Information System (INIS)

Myers, D.K.

1997-01-01

Regulation of radiological hazards to humans is greatly simplified by the existence of the International Commission on Radiological Protection (ICRP). The average RBE values or radiation weighting factors recommended by the ICRP are based on non-human data. The ICRP has also indicated that 'the standard of environmental control needed to protect man to the degree currently thought desirable will ensure that other species are not put at risk.' This statement appears to be supported by technical publications from other organizations. Two published objections by AECB staff to the scientific technical background of the ICRP statement do not offer any good reason to reject this ICRP statement. A brief summary is given of the joint working group report on the topic indicated in the title. It is noted that regulators of cancer-causing chemicals have in general paid less attention to natural sources than have the regulators of radiological hazards. Most non-human species are exposed to about 1 millisievert (mSv) equivalent dose of radiation per year from natural sources. Caribou and organisms living underground are noted as examples where radiation exposures from natural sources are considerably higher. The natural biota is in general remarkably resistant, both in the laboratory and in field studies, to the effects of high doses of radiation. A recent review by the International Atomic Agency concluded that dose rates below the equivalent of 400 mSv per year are unlikely to after the survival of non-human species. It is recommended that caution and common sense be applied in any future research on radiological protection of non-human species in the environment in Canada. Many of the proposed U.S. regulations to control chemical and radiation in the environment are not cost-effective. It is to be hoped that efforts to protect non-human species from potential radiological hazards in Canada do not slide into a similar kind of irrational quagmire. (author)

Risk of Hematopoietic and Lymphoproliferative Malignancies among U. S. Radiologic Technologists

International Nuclear Information System (INIS)

Linet, M. S.; Fredman, D. M.; Mohan, A.; Morin Doody, M.; Ron, E.; Mabuchi, K.; Alexander, B. B.; Sigurdson, A.; Matanoski, G.; Hauptmann, M.

2004-01-01

To evaluate risks of hematopoietic and lymphoproliferative malignancies among medical workers exposed to protracted low-to-moderate-dose radiation exposures, a follow-up investigation was conducted in a nation wide cohort of U. S. radiologic technologists. eligible for this study were 71.894 technologists (78% female) certified for at least 2 years during 1926-82, who had responded to a baseline mail questionnaire during 1983-89, were cancer-free except for non-melanoma skin cancer at completion of the questionnaire, and completed a second questionnaire during 1994-98 or died through August 1998. There were 241 technologists with hematopoietic or lymphoproliferative malignancies, including 41 with leukemia subtypes associated with radiation exposures (specifically acute myeloid, acute lymphoid and chronic myeloid leukemias, hereafter designated radiogenic leukemias), 23 with chronic lymphocytic leukemia, 28 with multiple myeloma, 118 with non-Hodgkin lymphoma, and 31 with Hodgkin lymphoma. Of the 241 hematopoietic or lymphoproliferative malignancies identified among radiologic technologists, 85 percent were confirmed by medical records or death certificates, including 98 percent of radiogenic leukemia. Risks of the hematopoietic or lymphoproliferative malignancies were evaluated in relation to questionnaire-derived information on employment as a radiologic technologist, including procedures, work practices, and protective measures. cox proportional hazards regression analysis was used to compute relative risks and 95% confidence intervals, using age at diagnosis as the response, stratifying at baseline for birth cohort in 5-year intervals, and adjusting for potential confounding. Risks were not increased for any of the hematopoietic or lymphoproliferative neoplasms according to year first worked or total duration of years worked as radiologic technologist. For the combined radiogenic leukemias, risks rose significantly with an increasing number of years worked

Determination of action zone in the nuclear / radiology handling process

International Nuclear Information System (INIS)

Ade Awalludin

2013-01-01

Assessment has been conducted on determination of action zone in nuclear or radiological emergency. The assessment is taken into account radiological risk level in nuclear or radiological emergency management process outside nuclear installation. Managing of nuclear emergency is same as that one of other emergency by adding the principles of radiation protection. This study aims to provide guidance in making of safety and security perimeter outside the nuclear installation for first responders during nuclear/radiological emergency based on dose rate, contamination level or distance from the scene. Separation of working zone is important for first responder safety that works in radiological environment in the event of nuclear or radiation emergency without violating their standard operating procedure. Value limit of safety and security perimeter has been made according to the conditions in Indonesia and considering the applicability in practical. (author)

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

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

Radiology resident MR and CT image analysis skill assessment using an interactive volumetric simulation tool - the RadioLOG project

International Nuclear Information System (INIS)

Gondim Teixeira, Pedro Augusto; Leplat, Christophe; Cendre, Romain; Hossu, Gabriela; Felblinger, Jacques; Blum, Alain; Braun, Marc

2017-01-01

Assess the use of a volumetric simulation tool for the evaluation of radiology resident MR and CT interpretation skills. Forty-three participants were evaluated with a software allowing the visualisation of multiple volumetric image series. There were 7 medical students, 28 residents and 8 senior radiologists among the participants. Residents were divided into two sub-groups (novice and advanced). The test was composed of 15 exercises on general radiology and lasted 45 min. Participants answered a questionnaire on their experience with the test using a 5-point Likert scale. This study was approved by the dean of the medical school and did not require ethics committee approval. The reliability of the test was good with a Cronbach alpha value of 0.9. Test scores were significantly different in all sub-groups studies (p < 0.0225). The relation between test scores and the year of residency was logarithmic (R"2 = 0.974). Participants agreed that the test reflected their radiological practice (3.9 ± 0.9 on a 5-point scale) and was better than the conventional evaluation methods (4.6 ± 0.5 on a 5-point scale). This software provides a high quality evaluation tool for the assessment of the interpretation skills in radiology residents. (orig.)

Radiology resident MR and CT image analysis skill assessment using an interactive volumetric simulation tool - the RadioLOG project

Energy Technology Data Exchange (ETDEWEB)

Gondim Teixeira, Pedro Augusto; Leplat, Christophe [CHRU-Nancy Hopital Central, Service d' Imagerie Guilloz, Nancy (France); Universite de Lorraine, IADI U947, Nancy (France); Cendre, Romain [INSERM, CIC-IT 1433, Nancy (France); Hossu, Gabriela; Felblinger, Jacques [Universite de Lorraine, IADI U947, Nancy (France); INSERM, CIC-IT 1433, Nancy (France); Blum, Alain [CHRU-Nancy Hopital Central, Service d' Imagerie Guilloz, Nancy (France); Braun, Marc [CHRU-Nancy Hopital Central, Service de Neuroradiologie, Nancy (France)

2017-02-15

Assess the use of a volumetric simulation tool for the evaluation of radiology resident MR and CT interpretation skills. Forty-three participants were evaluated with a software allowing the visualisation of multiple volumetric image series. There were 7 medical students, 28 residents and 8 senior radiologists among the participants. Residents were divided into two sub-groups (novice and advanced). The test was composed of 15 exercises on general radiology and lasted 45 min. Participants answered a questionnaire on their experience with the test using a 5-point Likert scale. This study was approved by the dean of the medical school and did not require ethics committee approval. The reliability of the test was good with a Cronbach alpha value of 0.9. Test scores were significantly different in all sub-groups studies (p < 0.0225). The relation between test scores and the year of residency was logarithmic (R{sup 2} = 0.974). Participants agreed that the test reflected their radiological practice (3.9 ± 0.9 on a 5-point scale) and was better than the conventional evaluation methods (4.6 ± 0.5 on a 5-point scale). This software provides a high quality evaluation tool for the assessment of the interpretation skills in radiology residents. (orig.)

Assessment of human and ecological risks from uranium and gold mining activities

International Nuclear Information System (INIS)

Hart, D.; McKee, P.; Garisto, N.

1995-01-01

Forecasting of ecological and human health risk has been widely used in the uranium mining industry to support decisions regarding acceptability of proposed mine developments and mine closure plans. Probabilistic assessment has been less frequently used in other mining sectors where radiological issues are less prominent, but is now beginning to be more broadly applied. Case studies are presented to illustrate probabilistic approaches in opening and closing assessments of uranium and gold mines. Risks to man and biota from operational emissions (radionuclides, arsenic, cyanide) and risk reductions following mine closure are forecast using probabilistic models of chemical fate, transport and exposure. These forecasts permit selection of operational and closure alternatives which produce acceptably low risks

Strengthening the scientific basis of radiological protection

International Nuclear Information System (INIS)

Lazo, Edward

2016-01-01

, 1998 and 2007). With these analyses, the CRPPH has assessed the possible implications that emerging scientific results (e.g. recent findings on radiation effects on the lens of the eye), or that possible results (e.g. ongoing epidemiological studies that could show statistically significant cancer risks, or that could show no cancer risks at doses below 50 mSv) could have for the way that radiological protection is regulated and applied. The latest report in this series, Radiological Protection Science and Application (NEA, 2016), performs such an assessment for today's level of scientific understanding. (author)

Assessment of risk of potential exposures on facilities industries

International Nuclear Information System (INIS)

Leocadio, Joao Carlos

2007-03-01

This work develops a model to evaluate potential exposures on open facilities of industrial radiography in Brazil. This model will decisively contribute to optimize operational, radiological protection and safety procedures, to prevent radiation accidents and to reduce human errors in industrial radiography. The probabilistic safety assessment (PSA) methodology was very useful to assess potential exposures. The open facilities of industrial radiography were identified as the scenario to be analyzed in what concerns the evaluation of potential exposures, due to their high accidents indices. The results of the assessment of potential exposures confirm that the industrial radiography in Brazil is a high-risk practice as classified by the IAEA. The risk of potential exposure was estimated to be 40,5 x 10 -2 per year in Brazil, having as main consequences injuries to the workers' hands and arms. In the world scene, the consequences are worst, leading to fatalities of people, thus emphasizing the high risk of industrial radiography. (author)

Assessment of the radiological impact of the inactive uranium-mill tailings at Grand Junction, Colorado

International Nuclear Information System (INIS)

Haywood, F.F.; Goldsmith, W.A.; Jacobs, D.G.; Perdue, P.T.; Ellis, B.S.; Hubbard, H.M. Jr.; Shinpaugh, W.H.

1980-04-01

Results of a radiological survey of the inactive uranium-mill site at Grand Junction, Colorado, made in May and June 1976, are presented along with descriptions of techniques and equipment used to obtain the data and an assessment of increased risk of health effects attributable to radiation and radionuclides from the tailings. An estimate of potential health effects of exposure to gamma rays around a former mill building and to radon daughters produced by radon dispersed from the tailings has been made for occupants of the site

Radiological risk assessment of U(nat) in the ground water around Jaduguda uranium mining complex

International Nuclear Information System (INIS)

Sethy, N.K.; Jha, V.N.; Shukla, A.K.; Tripathi, R.M.; Puranik, V.D.

2010-01-01

Uranium is present naturally in earth crust and hence at trace level in ground water, sea water, building materials etc. Naturally occurring radionuclide originating from industrial activities, metal mining and waste depository may contribute to the nearby ground water by radionuclide migration. Ground water ecosystem surrounding the uranium processing facility at Jaduguda has been studied for natural uranium distribution. In the present study, the drinking water sources at various distance zone (with in 1.6 km, 1.6-5 km and > 5km) covering all directions around the waste depository (tailings pond) have been investigated for uranium content. Evaluation of intake, ingestion dose and subsequent risk for population residing around the tailings pond has been carried out. Annual intake of uranium through drinking water for members of public residing around the uranium complex is found to be in the range of 41.8 - 44.4 Bq.y -1 . The intake and ingestion dose is appreciably low ( -1 ) which is far below the WHO recommended level of 100 Sv.y -1 . The life time radiological risk due to uranium natural in drinking water is insignificant and found to be of the order of 10 -6 . (author)

Risks from dental radiology; Os riscos provenientes da radiologia odontologica

Energy Technology Data Exchange (ETDEWEB)

Costa, Tamara Goularte [Instituto Federal de Educacao, Ciencia e Tecnologia de Santa Catarina (IFSC), Florianopolis (Brazil)

2013-10-01

The objective of this research is to demonstrate the risks and consequences of exposure to dental X-ray. The methodology used was the survey of bibliographic literature on this matter. First, we tried to understand the operation and characteristics of dental X-rays. Afterwards, we tried to know about the risks that this procedure offers to workers and patients. And concluded with the consequences of such exposure. The results showed that dental x-rays only offer risks in prolonged exposure, can affect the worker or patient to pathologies such as cancer or a life-time decreased due to the stochastic effect. Therefore, radiological protection standards must be respected and practised. (author)

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)

Risk perception of diagnostic and therapeutic radiological applications. Comparison of experts and the public

International Nuclear Information System (INIS)

Arranz, L.; Macias, M.T.; Prades, A.; Sola, R.; Martinez-Arias, R.

2000-01-01

Recent research has found many differences between experts and lay people in judgements of radiological risks. However, most of these studies were carried out on experts from nuclear power plants, regulatory bodies etc. This paper analyses the differences among several groups of 'experts' coming from the Health area and the lay people. A survey was designed to assess the perceived seriousness of seven diagnostic and therapeutic applications: conventional diagnostic radiology, computed tomography, chemotherapy, ecography examinations, radiotherapy, and diagnostic and therapeutic nuclear medicine. The questionnaire was distributed to samples of experts (professionals exposed to ionizing radiations, and other health professionals), and outpatients. All samples were selected from ten countries: Argentine, Brazil, Colombia, Cuba, Ecuador, Mexico, Panama, Peru, Uruguay, and Spain, thanks to the collaboration of the different National Radioprotection Societies of the above mentioned countries, and of other concerned professionals (in case they didn't have any association at the time). The following comparisons will be presented: 1) Differences between experts' and the public; 2) differences among several groups of 'experts'; 3) within the 'expert' sample, differences between perceived seriousness as a patient and as a professional at risk; 4) within the public sample, individual differences related to some socio-demographic variables. A cross-cultural analysis of the above mentioned comparisons will also be carried out. (author)

Risk perception of diagnostic and therapeutic radiological applications. Comparison of experts and the public

Energy Technology Data Exchange (ETDEWEB)

Arranz, L. [Hospital Ramon y Cajal, Madrid (Spain); Macias, M.T. [CSIC, Madrid (Spain); Prades, A.; Sola, R. [Ciemat, Madrid (Spain); Martinez-Arias, R. [Universidad Complutense, Madrid (Spain)

2000-05-01

Recent research has found many differences between experts and lay people in judgements of radiological risks. However, most of these studies were carried out on experts from nuclear power plants, regulatory bodies etc. This paper analyses the differences among several groups of 'experts' coming from the Health area and the lay people. A survey was designed to assess the perceived seriousness of seven diagnostic and therapeutic applications: conventional diagnostic radiology, computed tomography, chemotherapy, ecography examinations, radiotherapy, and diagnostic and therapeutic nuclear medicine. The questionnaire was distributed to samples of experts (professionals exposed to ionizing radiations, and other health professionals), and outpatients. All samples were selected from ten countries: Argentine, Brazil, Colombia, Cuba, Ecuador, Mexico, Panama, Peru, Uruguay, and Spain, thanks to the collaboration of the different National Radioprotection Societies of the above mentioned countries, and of other concerned professionals (in case they didn't have any association at the time). The following comparisons will be presented: 1) Differences between experts' and the public; 2) differences among several groups of 'experts'; 3) within the 'expert' sample, differences between perceived seriousness as a patient and as a professional at risk; 4) within the public sample, individual differences related to some socio-demographic variables. A cross-cultural analysis of the above mentioned comparisons will also be carried out. (author)

EPRI nuclear fuel-cycle accident risk assessment

International Nuclear Information System (INIS)

Anon.

1981-01-01

The present results of the nuclear fuel-cycle accident risk assessment conducted by the Electric Power Research Institute show that the total risk contribution of the nuclear fuel cycle is only approx. 1% of the accident risk of the power plant; hence, with little error, the accident risk of nuclear electric power is essentially that of the power plant itself. The power-plant risk, assuming a very large usage of nuclear power by the year 2005 is only approx. 0.5% of the radiological risk of natural background. The smallness of the fuel-cycle risk relative to the power-plant risk may be attributed to the lack of internal energy to drive an accident and the small amount of dispersible material. This work aims at a realistic assessment of the process hazards, the effectiveness of confinement and mitigation systems and procedures, and the associated likelihood of errors and the estimated size of errors. The primary probabilistic estimation tool is fault-tree analysis, with the release source terms calculated using physicochemical processes. Doses and health effects are calculated with CRAC (Consequences of Reactor Accident Code). No evacuation or mitigation is considered; source terms may be conservative through the assumption of high fuel burnup (40,000 MWd/t) and short cooling period (90 to 150 d); high-efficiency particulate air filter efficiencies are derived from experiments

Managing the radiological risk: ALARA, a principle, an obligation, a state of mind

International Nuclear Information System (INIS)

Lefaure, C.

1995-01-01

According to the 1993 data published by French nuclear operators and by the Ionizing Radiations Protection Office (OPRI), only two workers have exceeded the maximum annual permissible dose of 50 mSv. However, the respect of dose limits is not a sufficient warranty to accept the ionizing radiations exposure risk. The ALARA (As Low As Reasonably Achievable) principle is a masterpiece of the radiological protection system. Its goal is to maintain the exposures as low as reasonably achievable taking into account the socio-economical constraints. In France, the application of this principle is as compulsory as the respect of dose limits. The proper management and optimization of radiological risk requires the motivation of everybody. (J.S.). 2 refs., 3 figs

Generic performance assessment for a deep repository for low and intermediate level waste in the UK - a case study in assessing radiological impacts on the natural environment

International Nuclear Information System (INIS)

Jones, S.R.; Patton, D.; Copplestone D.; Norris, S.; O'Sullivan, P.

2003-01-01

Concentrations of radionuclides in soil and surface water, taken from a generic performance assessment of a repository for low and intermediate level radioactive waste, assumed to be located in the UK, have been used as the basis for a case study in assessing radiological impacts on the natural environment. Simplified descriptions of the terrestrial and aquatic ecosystem types likely to be impacted have been developed. A scoping assessment has identified 226 Ra, 210 Po, 234 U, 230 Th and 238 U as having the highest potential for impact, with doses from internally incorporated alpha emitters as being potentially of particular importance. These nuclides, together with 36 Cl and 129 I (which have proved to be of importance in radiological risk assessments for humans) were included in a more detailed dose assessment. A basic methodology for dose assessment of ecosystems is described, and has been applied for the defined impacted ecosystems. Paucity of published data on concentration factors prevented a more detailed assessment for terrestrial ecosystems. For the aquatic ecosystem, a more detailed assessment was possible and highest calculated absorbed dose rates (weighted for the likely higher biological effectiveness of alpha radiation were about 6.5 μGy h -1 . We conclude that harm to the impacted ecosystems is unlikely and make the observation that the lack of concentration factor or transfer factor data for a sufficiently wide range of species, ecosystems and nuclides appears to be the principal obstacle to establishing a comprehensive framework for the application of radiological protection to ecosystems

Assessment of Natural Radioactivity Levels and Potential Radiological Risks of Common Building Materials Used in Bangladeshi Dwellings.

Science.gov (United States)

Asaduzzaman, Khandoker; Mannan, Farhana; Khandaker, Mayeen Uddin; Farook, Mohideen Salihu; Elkezza, Aeman; Amin, Yusoff Bin Mohd; Sharma, Sailesh; Abu Kassim, Hasan Bin

2015-01-01

The concentrations of primordial radionuclides (226Ra, 232Th and 40K) in commonly used building materials (brick, cement and sand), the raw materials of cement and the by-products of coal-fired power plants (fly ash) collected from various manufacturers and suppliers in Bangladesh were determined via gamma-ray spectrometry using an HPGe detector. The results showed that the mean concentrations of 226Ra, 232Th and 40K in all studied samples slightly exceeded the typical world average values of 50 Bq kg(-1), 50 Bq kg(-1) and 500 Bq kg(-1), respectively. The activity concentrations (especially 226Ra) of fly-ash-containing cement in this study were found to be higher than those of fly-ash-free cement. To evaluate the potential radiological risk to individuals associated with these building materials, various radiological hazard indicators were calculated. The radium equivalent activity values for all samples were found to be lower than the recommended limit for building materials of 370 Bq kg(-1), with the exception of the fly ash. For most samples, the values of the alpha index and the radiological hazard (external and internal) indices were found to be within the safe limit of 1. The mean indoor absorbed dose rate was observed to be higher than the population-weighted world average of 84 nGy h(-1), and the corresponding annual effective dose for most samples fell below the recommended upper dose limit of 1 mSv y(-1). For all investigated materials, the values of the gamma index were found to be greater than 0.5 but less than 1, indicating that the gamma dose contribution from the studied building materials exceeds the exemption dose criterion of 0.3 mSv y(-1) but complies with the upper dose principle of 1 mSv y(-1).

Computer-Aided Nodule Assessment and Risk Yield Risk Management of Adenocarcinoma: The Future of Imaging?

Science.gov (United States)

Foley, Finbar; Rajagopalan, Srinivasan; Raghunath, Sushravya M; Boland, Jennifer M; Karwoski, Ronald A; Maldonado, Fabien; Bartholmai, Brian J; Peikert, Tobias

2016-01-01

Increased clinical use of chest high-resolution computed tomography results in increased identification of lung adenocarcinomas and persistent subsolid opacities. However, these lesions range from very indolent to extremely aggressive tumors. Clinically relevant diagnostic tools to noninvasively risk stratify and guide individualized management of these lesions are lacking. Research efforts investigating semiquantitative measures to decrease interrater and intrarater variability are emerging, and in some cases steps have been taken to automate this process. However, many such methods currently are still suboptimal, require validation and are not yet clinically applicable. The computer-aided nodule assessment and risk yield software application represents a validated tool for the automated, quantitative, and noninvasive tool for risk stratification of adenocarcinoma lung nodules. Computer-aided nodule assessment and risk yield correlates well with consensus histology and postsurgical patient outcomes, and therefore may help to guide individualized patient management, for example, in identification of nodules amenable to radiological surveillance, or in need of adjunctive therapy. Copyright © 2016 Elsevier Inc. All rights reserved.

Risk assessment of radiation carcinogenesis

International Nuclear Information System (INIS)

Kai, Michiaki

2012-01-01

This commentary describes the radiation cancer risk assessed by international organizations other than ICRP, assessed for radon and for internal exposure, in the series from the aspect of radiation protection of explaining the assessments done until ICRP Pub. 103. Statistic significant increase of cancer formation is proved at higher doses than 100-200 mSv. At lower doses, with use of mathematical model, United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) reported the death probability due to the excess lifetime risk (ELR) at 100 mSv of 0.36-0.77% for solid tumors and 0.03-0.05% for leukemia, and NRC in US, the risk of exposure-induced prevalence and death (REID) per 100 thousands persons of 800 (male)/1,310 (female) and 410/610, respectively. Both are essentially based on findings in A-bomb survivors. The assessment for Rn is described here not on dose. UK and US analyses of pooled raw data in case control studies revealed the significant increase of lung cancer formation at as low level as 100 Bq Rn/m3. Their analyses also showed the significance of smoking, which had been realized as a confounding factor in risk analysis of Rn for uranium miners. The death probability until the age of 85 y was found to be 1.2 x 10 -4 in non-smokers and 24 x 10 -4 in smokers/ Working Level Month (WLM). Increased thyroid cancer incidence has been known in Chernobyl Accident, which is realized as a result of internal exposure of radioiodine; however, the relationship between the internal dose to thyroid and its cancer prevalence resembles that in the case of external exposure. There is no certain evidence against the concept that risk of internal exposure is similar to and/or lower than, the external one although assessment of the internal exposure risk accompanies uncertainty depending on the used model and ingested dose. International Commission on Radiological Protection (ICRP) recommendations hitherto have been important and precious despite

MARC - the NRPB methodology for assessing radiological consequences of accidental releases of activity

International Nuclear Information System (INIS)

Clarke, R.H.; Kelly, G.N.

1981-12-01

The National Radiological Protection Board has developed a methodology for the assessment of the public health related consequences of accidental releases of radionuclides from nuclear facilities. The methodology consists of a suite of computer programs which predict the transfer of activity from the point of release to the atmosphere through to the population. The suite of programs is entitled MARC; Methodology for Assessing Radiological Consequences. This report describes the overall framework and philosophy utilised within MARC. (author)

ERRAPRI Project: estimation of radiation risk to patients in interventional radiology, initial results and proposed levels of complexity; Proyecto ERRAPRI: estimacion del riesgo radiologico a los pacientes en radiologia intervencionista. Primeros resultados y propuestas de indices de complejidad

Energy Technology Data Exchange (ETDEWEB)

Ruiz Cruces, R.; Vano, E.; Hernandez-Armas, J.; Carrera, F.; Diaz, F.; Gallego Beuther, J. F.; Ruiz Munoz-Canela, J. P.; Sanchez Casanueva, R.; Perez Martinez, M.; Fernandez Soto, J. M.; Munoz, V.; Moreno, F.; Moreno, C.; Martin-Palanca, A.

2011-07-01

The project ERRAPRI (2009 - 2012) will assess the most relevant aspects of the radiological risk associated with interventional radiology techniques (IR) guided by fluoroscopy in a sample of Spanish hospitals of three autonomous regions. Specific objectives include: assessing procedural protocols, especially the parameters related to radiation dose and diagnostic information obtained to establish balances cost (radiation risk) benefit to the procedures evaluated, and propose an index of complex procedures on several levels, based on the difficulty of making the same, assessing its relationship with the radiation dose values.

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

Development and application of portable mobile gamma spectrometry system (PMGSS) for realtime online radiological assessment

International Nuclear Information System (INIS)

Patil, S.S.; Padmanabhan, N.; Sharma, R.; Singh, R.; Pradeepkumar, K.S.

2008-01-01

A state of art mobile monitoring system is a prime requirement to combat the challenging radiological situations. In the event of any radiological/nuclear Emergencies an effective, realistic methodology of radiological measurements is an asset. In this context, a highly sensitive real-time online mobile monitoring system having features and provision to display the important parameters will be an essential tool in the course of radiological impact assessment. This paper, describes the efforts that has been made towards providing a useful Portable Mobile Gamma Spectrometry System (PMGSS) and developing applications so as to enhance its usefulness in quick radiological impact assessment and to initiate the proper countermeasures during any Nuclear/Radiological emergency situation in public domain. The system uses a NaI(Tl) detector, a global positioning system (GPS) and a laptop PC for storage, analysis and graphical representation of the acquired data. PMGSS is a highly sensitive, portable and reliable radiation monitoring equipment with capability of qualitative and quick estimation of the radioisotopes. The system was used for the mobile radiological mapping of Bangalore and Mumbai city and demonstrated its capability for use in environmental radiation monitoring during any radiological emergency requirement the results of which are presented here. (abstract)

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

Radiological Protection Criteria for the Safety of LILW Repository in Croatia

International Nuclear Information System (INIS)

Levanat, I.; Lokner, V.; Subasic, D.

2000-01-01

Preparations for a LILW repository development in Croatia, conducted by APO Hazardous Waste Management Agency, have reached a point where the first safety assessment of the prospective facility is being attempted. For evaluation of the calculated radiological impact in the assessed option of repository development, a set of radiological protection criteria should be included in the definition of the assessment context. The Croatian regulations do not explicitly require that the repository development be supported by such safety assessment process, and do not provide a specific set of radiological criteria intended for the repository assessment which would be suitable for the constrained optimization of protection. For the initial safety assessment iterations of the prospective repository, which will address long term performance of the facility for various design and other safety options, we propose to use relatively simple radiological protection criteria, consisting only of individual dose and risk constraints for the general population. The numerical values for these constraints are established in accordance with the recognized international recommendations and in compliance with all possibly relevant Croatian safety requirements. (author)

Radiological impacts from nuclear facilities on non-human species

International Nuclear Information System (INIS)

1997-07-01

This monograph is the Proceedings of a Symposium on Radiological Impacts from Nuclear Facilities on Non-Human Species, held in Ottawa, Canada, December 1 and 2, 1996. The Symposium was held in response to the assessment of radiological impacts from nuclear facilities on non-human biota by Environment Canada and the move by Atomic Energy Control Board to include the radiological impacts in its regulatory regime. The two major goals of the Symposium were to critically evaluate the ecological risk assessment as applied to radionuclides and contribute to the wide consultation sought by the Atomic Energy Control Board on their new environmental initiatives. The series of papers presented at the Symposium discuss issues relevant to the two major objectives of the Symposium

Excess Cancer Risk Assessment from Some Common X-Ray Examinations in Sabzevar County

Directory of Open Access Journals (Sweden)

Mohammad Taghi Bahreyni Toossi

2011-09-01

Full Text Available Introduction: Nowadays ionizing radiation has a considerable contribution in medical diagnostic and treatment. Using ionizing radiation is increasing rapidly, so biological effects of ionizing radiation should be considered more. X-rays in the range of diagnostic radiology have hazardous effects and risks that are defined as random effects. These effects obey the LNT hypothesis that occur at low doses and include many types of cancer and genetic mutations. So it is very important to assess the risk of exposure in medical examinations. Cancer is one of these hazardous risks caused by low dose ionizing radiation that may occur during life after exposure. According to BEAR 7, low dose radiation is defined as radiation that produces doses near zero up to 100 mSv. Materials and Methods: This work was carried out in eight radiology centers in the Sabzevar county of Iran for 485 patients in eight typical x-ray examinations chosen for the study: chest PA, chest AP, lumbar spine AP, lumbar spine LAT, pelvis AP, abdomen AP, skull AP and Lat. In order to estimate the excess cancer risk, we need to obtain collective effective dose caused by radiation in the study population. Usually effective dose offers precise assessment of radiography examination injuries in adult patients. In this study, we used the PCXMC Monte Carlo based software to obtain effective dose and organ dose. This software calculates organ and effective dose following input of patient and radiographic conditions. Results: Average patient weight and height, entrance surface dose, parameters used for each type of examination, and DAP values were entered. Effective dose, collective effective dose, number of radiographs per year and the excess cancer risk arising from these radiographic examinations were then calculated.  Discussion and Conclusion: Excess risk of fatal cancer due to x-ray examinations in the study population was calculated by collective effective dose. This risk in the

An attempt to evaluate the risks associated with radiological terror

International Nuclear Information System (INIS)

Paschoa, A.S.; Dantas, B.M.

2014-01-01

The evaluation of the risk of a terrorist attack has been made frequently by multiplying the probability of occurrence of a terrorist attempt by the probability of its success and a quantity which represents the consequences of a successful attack. In the case of a radiological attack the consequences will vary in case the action will be active or passive. Thirteen radionuclides were examined for their potential uses in credible threats or terrorist attacks based on their availability from laboratories and hospitals. Taking into account the dose conversion coefficients published by the International Atomic Energy Agency, those radionuclides with higher dose effectiveness for ingestion are the following: 210 Po; 226 Ra and 241 Am. Other radionuclides which can be used in threats and terror attacks, like 137 Cs for example have also been examined. The risks associated with the selected radionuclides have been tentatively ranked as high, medium, or low. The probability used to evaluate risks depends on the motivation of the terrorist and the capacity, which implies availability or the actual possibility of obtaining a particular radionuclide. On the other hand, whenever a list of radionuclides to be used in a malevolent action is available to a terrorist, the choice of the most adequate will depend also on the action to be undertaken. This work ranks risks associated with radiological terror based on physical, chemical, radio-toxicological and other relevant data on radionuclides, which were either already used in terror attacks, or were pointed out as adequate to be used in such malevolent actions. (author)

Correlation of radiological assessment of congestive heart failure with left ventricular end-diastolic pressure

International Nuclear Information System (INIS)

Herman, P.G.; Kahn, A.; Kallman, C.E.; Rojas, K.A.; Bodenheimer, M.M.

1988-01-01

Left ventricular end-diastolic pressure (LVEDP) has been considered a reliable indicator of left ventricular function. The purpose of this study was to correlate the radiologic assessment of congestive heart failure with LVEDP. The population of the study consisted of 85 consecutive cases in four ranges of LVEDP ( 24). The PA chest radiographs obtained 1 day prior to cardiac catherization were assessed for radiological evidence of congestive heart failure and were graded from normal to abnormal (0-3). The results will be summarized in the authors' presentation. The discordance of radiological assessment of congestive heart failure in patients with elevated LVEDP will be discussed in light of recent advances in pathophysiologic understanding of left ventricular function and the impact of new classes of drugs in the management of these patients

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

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.

Patients as partners in radiology education: an innovative approach to teaching and assessing patient-centered communication.

Science.gov (United States)

Lown, Beth A; Sasson, J Pierre; Hinrichs, Peg

2008-04-01

Effective communication is essential for high quality care, yet little is known about radiologists' communication with patients, what constitutes "best communication practices," and how best to teach and evaluate it. We piloted educational strategies and an assessment instrument to teach and evaluate radiologists' communication skills. We focused on communication in the diagnostic mammography suite, where patient-radiologist interactions are often intense and stressful. We adapted existing instruments to create a Radiology Communication Skills Assessment Tool (RCSAT). We piloted an educational program that included patients as teachers and raters of interpersonal and communication skills, and implemented a radiology objective structured clinical examination (OSCE). We measured radiology residents' self-assessed skills, confidence and stress, as well as patient-rated communication skills using the RCSAT. Residents' baseline self-assessed communication skills regarding abnormal mammograms were fair, confidence in their communication was minimal, and they found this communication stressful. Overall baseline communication skills, rated by patient-teachers using the RCSAT, were 3.62 on a 5-point scale (1 = poor to 5 = excellent). Analysis of post-OSCE debriefing comments yielded nine themes regarding effective radiology communication, as well as residents' reflections on the communication challenges they experience. The themes were integrated into subsequent RCSAT revisions. Residents' reflections were used to inform teaching workshops. Educational curricula on communication about difficult information can be implemented in radiology training programs. Radiology residents' performance can be assessed using a communication skills assessment tool during standardized patient-teacher encounters. Further research is necessary in this important domain.

Information about radiation dose and risks in connection with radiological examinations: what patients would like to know

International Nuclear Information System (INIS)

Ukkola, Leila; Oikarinen, Heljae; Haapea, Marianne; Tervonen, Osmo; Henner, Anja; Honkanen, Hilkka

2016-01-01

To find out patients' wishes for the content and sources of the information concerning radiological procedures. A questionnaire providing quantitative and qualitative data was prepared. It comprised general information, dose and risks of radiation, and source of information. Two tables demonstrating different options to indicate the dose or risks were also provided. Patients could give one or many votes. Altogether, 147 patients (18-85 years) were interviewed after different radiological examinations using these devices. 95 % (139/147) of the patients wished for dose and risk information. Symbols (78/182 votes) and verbal scale (56/182) were preferred to reveal the dose, while verbal (83/164) and numerical scale (55/164) on the risk of fatal cancer were preferred to indicate the risks. Wishes concerning the course, options and purpose of the examination were also expressed. Prescriber (3.9 on a scale 1-5), information letter (3.8) and radiographer (3.3) were the preferred sources. Patients aged 66-85 years were reluctant to choose electronic channels. Apart from general information, patients wish for dose and risk information in connection with radiological examinations. The majority preferred symbols to indicate dose and verbal scales to indicate risks, and the preferred source of information was the prescriber or information letter. (orig.)

Research and development in radiological protection; Investigacion y desarrollo en proteccion radiologica

Energy Technology Data Exchange (ETDEWEB)

Butragueno, J. L.; Villota, C.; Gutierrez, C.; Rodriguez, A.

2004-07-01

The objective of Radiological Protection is to gurantee that neither people, be they workers or members of the public, or the environment are exposed to radiological risks considered by society to be unacceptable. Among the various resources available to meet this objective is Research and Development (R and D), which is carried out in three areas: I. Radiological protection of persons: (a) knowledge of the biological effects of radiations, in order to determine the relationship that exists between radiation exposure dose and its effects on health; (b) the development of new personal dosimetry techniques in order to adapt to new situations, instrumental techniques and information managmenet technologies allowing for better assessment of exposure dose; and (c) development of the principle of radiological protection optimisation (ALARA), which has been set up internationally as the fundamental principle on which radiological protection interventions are based. II. Assessment of environmental radiological impact, the objective of which is to assess the nature and magnitude of situations of exposure to ionising radiations as a result of the controlled or uncontrolled release of radioactive material to the environment, and III.Reduction of the radiological impact of radioactive wastes, the objective of which is to develop radioactive material and waste management techniques suitable for each situation, in order to reduce the risks assocaited with their definitive managmenet or thier release to the environment. Briefly desribed below are the strategic lines of R and D of the CSN, the Electricity Industry, Ciemat and Enresa in the aforementioned areas. (Author)

Assessment of the radiological risks of underground disposal of solid radioactive wastes

International Nuclear Information System (INIS)

Thorne, M.C.

1988-12-01

One of the general principles for assessing proposals for operating a landbased facility for solid radioactive waste disposal is that the site should be chosen and the facility should be designed so that the risk or probability of fatal cancer, to any member of the public, from any movement of radioactivity from the facility, is not greater than 1 in a million in any one year. This report provides advice to the Department of the Environment as to how this risk may be defined and gives a prescription for how it can be calculated. (author)

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

CEA: assessment of risk management 2011

International Nuclear Information System (INIS)

2012-06-01

This report proposes an overview of CEA activities in the field of risk management in different areas: impact on the environment, installation safety, management of occupational risks (occupational health and safety), radiological protection of workers, transportation of hazardous materials, waste management, protection of sites, installations and heritage, management of emergency situations, management of law risks, controls and audits. It finally presents the risk management department

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.

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

Risk assessment in the DOE Assurance Program for Remedial Action

International Nuclear Information System (INIS)

Marks, S.; Cross, F.T.; Denham, D.H.; Kennedy, W.E.; Stenner, R.D.

1985-08-01

This document provides information obtained during the performance of risk assessment tasks in support of the Assurance Program for Remedial Action (APRA) sponsored by the Office of Operational Safety of the Department of Energy. We have presented a method for the estimation of projected health effects at properties in the vicinity of uranium mill tailing piles due to transported tailings or emissions from the piles. Because radon and radon daughter exposure is identified as the principal factor contributing to health effects at such properties, the basis for estimating lung cancer risk as a result of such exposure is discussed in detail. Modeling of health risk due to a secondary pathway, ingestion of contaminated, home-grown food products, is also discussed since it is a potentially important additional source of exposure in certain geographic locations. Risk assessment methods used in various mill tailings reports are reviewed. The protocols for radiological surveys conducted in DOE-sponsored remedial action programs are critically reviewed with respect to their relevance to the needs of health risk estimation. The relevance of risk assessment to the APRA program is discussed briefly

Assessment of Transportation Risk of Radioactive Materials in Uganda

International Nuclear Information System (INIS)

Richard, Menya; Kim, Jonghyun

2014-01-01

Radioactive materials refer to any materials that spontaneously emit ionizing radiation and of which the radioactivity per gram is greater than 0.002 micro-curie. They include: spent nuclear fuel, nuclear wastes, medical sources i.e. Co-60, industrial sources i.e. Cs-137, Am-241:Be, Ra-226, and sources for research. In view of the rising reported cancer cases in Uganda, which might be as a result of radiation exposure due to constant transportation of radioactive materials i.e. industrial sources, a risk analysis was thought of and undertaken for the country's safety evaluation and improvement. It was therefore important to undertake a risk assessment of the actual and potential radiation exposure during the transportation process. This paper explains a study undertaken for transport risk assessment of the impact on the environment and the people living in it, from exposure to radioactivity during transportation of the industrial sources in Uganda. It provides estimates of radiological risks associated with visualized transport scenarios for the highway transport mode. This is done by calculating the human health impact and radiological risk from transportation of the sources along Busia transport route to Hoima. Busia is the entry port for the sources whilst Hoima, where various industrial practices that utilize sources like oil explorations are centered. During the study, a computer code RADTRAN-6 was used. The overall collective dose for population and package transport crew are 3.72E-4 and 1.69E-4 person-sievert respectively. These are less than the exemption value recommended by the IAEA and Uganda Regulatory Authority for public implying that no health effects like cancer are to be expected. Hence the rising cancer cases in the country are not as a result of increased transportation of radioactive materials in the Industrial sector

Assessment of Transportation Risk of Radioactive Materials in Uganda

Energy Technology Data Exchange (ETDEWEB)

Richard, Menya; Kim, Jonghyun [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

2014-10-15

Radioactive materials refer to any materials that spontaneously emit ionizing radiation and of which the radioactivity per gram is greater than 0.002 micro-curie. They include: spent nuclear fuel, nuclear wastes, medical sources i.e. Co-60, industrial sources i.e. Cs-137, Am-241:Be, Ra-226, and sources for research. In view of the rising reported cancer cases in Uganda, which might be as a result of radiation exposure due to constant transportation of radioactive materials i.e. industrial sources, a risk analysis was thought of and undertaken for the country's safety evaluation and improvement. It was therefore important to undertake a risk assessment of the actual and potential radiation exposure during the transportation process. This paper explains a study undertaken for transport risk assessment of the impact on the environment and the people living in it, from exposure to radioactivity during transportation of the industrial sources in Uganda. It provides estimates of radiological risks associated with visualized transport scenarios for the highway transport mode. This is done by calculating the human health impact and radiological risk from transportation of the sources along Busia transport route to Hoima. Busia is the entry port for the sources whilst Hoima, where various industrial practices that utilize sources like oil explorations are centered. During the study, a computer code RADTRAN-6 was used. The overall collective dose for population and package transport crew are 3.72E-4 and 1.69E-4 person-sievert respectively. These are less than the exemption value recommended by the IAEA and Uganda Regulatory Authority for public implying that no health effects like cancer are to be expected. Hence the rising cancer cases in the country are not as a result of increased transportation of radioactive materials in the Industrial sector.

CEA: risk management assessment 2011

International Nuclear Information System (INIS)

Bigot, Bernard; Bonnevie, Edwige; Maillot, Bernard

2012-01-01

This report proposes a qualitative and quantitative overview of CEA activities in the field of risk management during 2011. These activities concerned the impact on the environment, the safety of installations, the management of professional risks (safety and health at work), the radiological protection of workers, the transports of hazardous materials, waste management, protection of sites, installations and heritage, the management of emergency situations, the management of law risks, controls and audits

Prevalence of cancer risk factors among women radiologists and radiology assistants in Lithuania

International Nuclear Information System (INIS)

Samerdokiene, V.; Kurtinaitis, J.; Atkocius, V. and others

2005-01-01

The aim of the work was to study potential cancer risk factors among radiologists and non-radiologists in Lithuania. Cancer risk factors were investigated among female medical staff at the departments of ionizing (243, 33.33%) and non-ionizing environment (486, 66.67%). The questionnaire covered the diet, lifestyle, reproductive factors as well as the demographic and physical characteristics. Univariate analysis was done separately for physicians and nurses. Each of risk factors was evaluated in stratified analysis for unequal ORs using Mantel-Haenszel estimate control for age and occupation. Evaluation of features of risk factors among radiologists vs. non-radiologists has shown that smoking was most the prevalent risk factor among radiologists and radiology assistants. Despite the relatively low prevalence, the questionnaire data showed the higher frequency of smoking among radiologists (OR = 2.78, 95% CI 1.12-6.87) and radiology assistants (OR = 2.25, 95% 1.38-3.66) compared to non-radiologists. The prevalence of non-users and occasional users was 74% to 66%, respectively. Alcohol use by smoking among radiologists was influenced insignificantly. The cohort of radiologists in Lithuania offer an opportunity for obtaining direct observational evidence on health effects associated with chronic low-dose radiation exposure. The data on possible cancer risk factors can be helpful for validation of the risks in future. (author)

Radiation monitoring systems and methodologies for radiological impact assessment

International Nuclear Information System (INIS)

Chaudhury, Probal

2016-01-01

Radioactive sources of various strengths are used in large number of applications in industry, healthcare, agriculture and research. Though all the sources are transported and used under regulatory control, there is always a possibility of some of the sources getting into the hands of committed antisocial non state actors. In addition to this, there is a possible threat of radioactive material being illegally brought into a country. These gives rise to an increase in the global radiological threat and security experts world over are concerned about the possibility of malicious use of radiation in the public domain. Radiation detection systems are installed at various entry and exit ports of some of the countries to detect illicit trafficking of radioactive materials. IAEA has recommended that all States should have a national response plan for nuclear security events to provide for an appropriate and coordinated response. Considering the requirement of radiological emergency preparedness, various radiation monitoring systems and methodologies have been developed. A few aerial radiation monitoring systems developed at Bhabha Atomic Research Centre (BARC) for radiological impact assessment are described here

PARALLELS OF RADIATION- AND FINANCIAL-RISK MANAGEMENT ON PUBLIC ACCEPTANCE

Energy Technology Data Exchange (ETDEWEB)

Hogue, M.

2010-01-04

The financial collapse of 2007 provides an opportunity for a cross-discipline comparison of risk assessments. Flaws in financial risk assessments bear part of the blame for the financial collapse. There may be a potential for similar flaws to be made in radiological risk assessments. Risk assessments in finance and health physics are discussed in the context of a broader view of the risk management environment. Flawed risk assessments can adversely influence public acceptance of radiological technologies, so the importance of quality is magnified.

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

A model for radiological risk assessment from transportation of radioactive material

International Nuclear Information System (INIS)

Mancioppi, S.; Piermattei, S.

1985-01-01

The transport of radioactive materials is an important step in every practice involving the use of nuclear energy. The record of safety until now attained is undoubtedly satisfactory; however being large quantities of radioactive substances transported every day throughout the world, it was deemed worthwhile to evaluate the radiological impact connected with the transport of radioactive materials. The International Atomic Energy Agency, as the Agency issuing the Regulations applied by almost all the national and international transport organizations, sponsored a study aimed to develop a model for the evaluation of the risk connected with the transport activity. A code INTERTRAN (International Transport) has been developed by a Swedish research group (1) and is mainly based on a code (Radtran) developed at Sandia Labs. Other research groups like US and Italy offered their cooperation in the preparation of the code. It appears that the collective dose equivalents involved in the shipments of all wastes to their hypothetical final destination are rather low (40 person-rem in the worst case) and do not depend strongly from the transport mode. Handlers and crew are the most exposed group as it was expected, while the dose contribution to the general public is negligible. The situation could change in case of accident as accident dynamic and accident rate strongly depend on the mode of transport; it might happen that in this case one transport mode could be preferred to another. It is therefore deemed very important to deserve great attention to accident analysis, taking into account also the fact that there exists a category of flammable waste. Our future studies are oriented in this direction

Proposed classification scale for radiological incidents and accidents

International Nuclear Information System (INIS)

2003-04-01

The scale proposed in this report is intended to facilitate communication concerning the severity of incidents and accidents involving the exposure of human beings to ionising radiations. Like the INES, it comprises eight levels of severity and uses the same terms (accident, incident, anomaly, serious and major) for keeping the public and the media informed. In a radiological protection context, the severity of an event is considered as being directly proportional to the risk run by an individual (the probability of developing fatal or non-fatal health effects) following exposure to ionising radiation in an incident or accident situation. However for society, other factors have to be taken into account to determine severity. The severity scale proposed is therefore based on assessment of the individual radiological risk. A severity level corresponding to exposure of a member of the public in an incident or accident situation is determined on the basis of risk assessment concepts and methods derived from international consensus on dose/effect relationships for both stochastic and deterministic effects. The severity of all the possible exposure situations - worker exposure, collective exposure, potential exposure - is determined using a system of weighting in relation to situations involving members of the public. In the case of this scale, to indicate the severity of an event, it is proposed to make use of the most penalizing level of severity, comparing: - the severity associated with the probability of occurrence of deterministic effects and the severity associated with the probability of occurrence of stochastic effects, when the event gives rise to both types of risk; - the severity for members of the public and the severity for exposed workers, when both categories of individuals are involved; - the severity on the proposed radiological protection scale and that obtained using the INES, when radiological protection and nuclear safety aspects are associated with

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

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

Radiological protection in interventional radiology

International Nuclear Information System (INIS)

Padovani, R.

2001-01-01

Interventional radiology (IR) reduces the need for many traditional interventions, particularly surgery, so reducing the discomfort and risk for patients compared with traditional systems. IR procedures are frequently performed by non-radiologist physicians, often without the proper radiological equipment and sufficient knowledge of radiation protection. Levels of doses to patients and staff in IR vary enormously. A poor correlation exists between patient and staff dose, and large variations of dose are reported for the same procedure. The occurrence of deterministic effects in patients is another peculiar aspect of IR owing to the potentially high skin doses of some procedures. The paper reviews the use of IR and the radiological protection of patients and staff, and examines the need for new standards for IR equipment and the training of personnel. (author)

Assessment of the radiological control at the IPEN radioisotope production facility

International Nuclear Information System (INIS)

Carneiro, Janete C.G.G.; Sanches, Matias P.; Rodrigues, Demerval L.; Campos, Daniela; Nogueira, Paulo R.; Damato, Sandra R.; Pecequilo, Brigitte R.

2014-01-01

The main objective of this work is to evaluate the 2013 annual radiological control results in the radiopharmaceuticals areas of the Instituto de Pesquisas Energeticas e Nucleares, IPEN/SP, and the environmental radiological impact, resulting from the practices there performed. The current evaluation was performed through the analysis of the results obtained from occupational and environmental monitoring with air samplers and TL dosimeters. All monitoring results were compared with the limits established by national standards. The radionuclides detected by air sampling (in charcoal and paper filters) at the workplace during radioisotope production were 131 I, 99m Tc and 99 Mo, with activities concentrations values below the annual limits values. For the radioactive gaseous releases (Bq/m 3 ), the activities concentrations also remained below the maximum permissible values, excepting to 125 I release due to an unusual event occurred in a researcher laboratory, but the radiological impact to environmental was no significant. The occupational monitoring assessment was confirmed by the Environmental Radiological Monitoring Program results with air samplers and TL dosimeters. The mean annual background radiation at IPEN in 2013, according to the Environmental Radiological Monitoring Program results was 1.06 mSv. y -1 , below the ICRP 103 recommended limit of 20 mSv.y -1 for workers. (author)

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)

Commercial low-level radioactive waste transportation liability and radiological risk

Energy Technology Data Exchange (ETDEWEB)

Quinn, G.J.; Brown, O.F. II; Garcia, R.S.

1992-08-01

This report was prepared for States, compact regions, and other interested parties to address two subjects related to transporting low-level radioactive waste to disposal facilities. One is the potential liabilities associated with low-level radioactive waste transportation from the perspective of States as hosts to low-level radioactive waste disposal facilities. The other is the radiological risks of low-level radioactive waste transportation for drivers, the public, and disposal facility workers.

Commercial low-level radioactive waste transportation liability and radiological risk

International Nuclear Information System (INIS)

Quinn, G.J.; Brown, O.F. II; Garcia, R.S.

1992-08-01

This report was prepared for States, compact regions, and other interested parties to address two subjects related to transporting low-level radioactive waste to disposal facilities. One is the potential liabilities associated with low-level radioactive waste transportation from the perspective of States as hosts to low-level radioactive waste disposal facilities. The other is the radiological risks of low-level radioactive waste transportation for drivers, the public, and disposal facility workers

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

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

Probabilistic risk assessment course documentation. Volume 7. Environmental transport and consequence analysis

International Nuclear Information System (INIS)

Ritchie, L.T.; Alpert, D.J.; Burke, R.P.; Ostmeyer, R.M.; Kaiser, G.D.; Runkle, G.E.; Woodard, K.

1985-08-01

Consequence models have been designed to assess health and economic risks from potential accidents at nuclear power plants. These models have been applied to an ever increasing variety of problems with ever increasing demands to improve modeling capabilities and provide greater realism. This course discusses the environmental transport of postulated radiological releases and the elements and purpose of accident consequence evaluation

Development of the CHEMTARD coupled process simulator for use in radiological assessment

International Nuclear Information System (INIS)

Liew, S.K.; Read, D.

1987-12-01

This report describes features of CHEMTARD (Chemical Transport Adsorption Redox and Decay); a directly-coupled chemical transport code, developed to aid the DOE in carrying out post-closure radiological risk assessments. The program is based on the Lawrence Berkeley code, CHEMTRN, and simulates the one-dimensional transport of aqueous chemical species by advection and/or diffusion while accounting for phase transfer by reversible precipitation-dissolution, ion-exchange or surface adsorption. New models for radioactive decay, oxidation-reduction reactions, flexible boundary conditions and multi-layered transport have significantly enhanced the ability of the code to perform coupled process calculations. Although originally developed for studies involving shallow disposal of low level wastes, the models contained in CHEMTARD are sufficiently general to allow thermodynamic treatment of chemical transport for porous flow through all saturated aquifer systems. (author)

Radiological accidents potentially important to human health risk in the U.S. Department of Energy waste management program

International Nuclear Information System (INIS)

Mueller, C.; Roglans-Ribas, J.; Folga, S.; Nabelssi, B.; Jackson, R.

1995-01-01

Human health risks as a consequence of potential radiological releases resulting from plausible accident scenarios constitute an important consideration in the US Department of Energy (DOE) national program to manage the treatment, storage, and disposal of wastes. As part of this program, the Office of Environmental Management (EM) is currently preparing a Programmatic Environmental Impact Statement (PEIS) that evaluates the risks that could result from managing five different waste types. This paper (1) briefly reviews the overall approach used to assess process and facility accidents for the EM PEIS; (2) summarizes the key inventory, storage, and treatment characteristics of the various DOE waste types important to the selection of accidents; (3) discusses in detail the key assumptions in modeling risk-dominant accidents; and (4) relates comparative source term results and sensitivities

Geostatistical methods for radiological evaluation and risk analysis of contaminated premises

International Nuclear Information System (INIS)

Desnoyers, Y.; Jeannee, N.; Chiles, J.P.; Dubot, D.

2009-01-01

Full text: At the end of process equipment dismantling, the complete decontamination of nuclear facilities requires the radiological assessment of residual activity levels of building structures. As stated by the IAEA, 'Segregation and characterization of contaminated materials are the key elements of waste minimization'. From this point of view, the set up of an appropriate evaluation methodology is of primordial importance. The radiological characterization of contaminated premises can be divided into three steps. First, the most exhaustive facility analysis provides historical, functional and qualitative information. Then, a systematic (exhaustive or not) control of the emergent signal is performed by means of in situ measurement methods such as surface control device combined with in situ gamma spectrometry. Besides, in order to assess the contamination depth, samples can be collected from boreholes at several locations within the premises and analyzed. Combined with historical information and emergent signal maps, such data improve and reinforce the preliminary waste zoning. In order to provide reliable estimates while avoiding supplementary investigation costs, there is therefore a crucial need for sampling optimization methods together with appropriate data processing techniques. The relevance of the geostatistical methodology relies on the presence of a spatial continuity for radiological contamination. In this case, geostatistics provides reliable methods for activity estimation, uncertainty quantification and risk analysis, which are essential decision-making tools for decommissioning and dismantling projects of nuclear installations. Besides, the ability of this geostatistical framework to provide answers to several key issues that generally occur during the clean-up preparation phase is discussed: How to optimise the investigation costs? How to deal with data quality issues? How to consistently take into account auxiliary information such as historical

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

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)

Methodological guide for risk assessment and management of industrial sites contaminated with radionuclides

International Nuclear Information System (INIS)

Oudiz, A.; Brenot, J.; Cessac, B.; Charbonneau, P.; Maigne, J.P.; Santucci, P.

2000-01-01

At the request of the French ministries of health and environment, IPSN was asked to elaborate a methodological guide for risk assessment and management of industrial sites contaminated with radionuclides. This guide is devoted to local administration, technical organisms and more generally to all the relevant stakeholders involved with the choice of a rehabilitation strategy, according to the future use of the site. The methodology to be presented is designed to fit with the different types of 'risk governance', according to circumstances: - when an industrial site is relatively small, with rather restricted zones of contamination, and no specific social concern, management may rely essentially upon radiological expertise, using generic reference levels, - when the site is larger, with spread out contamination, risk assessment and management of the site may become more controversial, namely because uncertainties remain about the effective magnitude of the contamination and no low cost solution appears to exist in view of rehabilitation. In this case, an open procedure is required, which combines technical expertise and involvement of stakeholders, in view of improving the risk assessment process as well as trying to get a better understanding of the benefits and drawbacks of different rehabilitation strategies. The methodology consists of six main steps : - Initiating the process, Pre-diagnosis, Initial diagnosis, Simplified risk assessment, Detailed risk assessment, Decision aiding in view of letting the stakeholders defining the solution appropriate to the local context. The paper will present how the risk assessment and management process can be aportionated to the importance of the problem to be solved. As far as possible, simplified risk assessment should provide information allowing the definition of the appropriate strategy. In this case, stakeholders involvement is mainly devoted to determine: - whether the site can be affected to a given use without

Radiological accidents, scenarios, planning and answers

International Nuclear Information System (INIS)

Solis Delgado, Alexander.

2008-01-01

Radiological accidents, scenarios and the importance of a good planning to prevent and control these types of accidents are presented. The radiation can be only one of the risks in an accident, most of dominant radiological risks are not radiological (fire, toxic gases, etc.). The common causes of radiological accidents, potential risks such as external irradiation, internal contamination and the environment pollution are highlighted. In addition, why accidents happen and how they evolve is explained. It describes some incidents with the radiation occurred in Costa Rica from 1993 to 2007. The coordination of emergency management in Costa Rica in relation to a radiological accident, and some mechanisms of action that have practiced in other places are focuses. Among the final considerations are the need to finalize the national plan for radiological emergencies as a tool of empowerment for the teams of emergency care and the availability of information. Likewise the processes of communication, coordination and cooperation to avoid chaos, confusion and crisis are also highlighted [es

Radiological risks of transports to central waste management facilities

International Nuclear Information System (INIS)

Lange, F.

1997-01-01

Transports of radioactive waste from nuclear facilities have been a matter of frequent public concern in the recent past. News reports, protests and questions concerning the radiological risk tended to concentrate on transports to and from central waste management facilities, e.g. transports of spent fuel elements to reprocessing plants abroad (France, England), transports to intermediate storage sites (Ahaus, Gorleben), transports to operative (Morsleben) and projected (Konrad) final storage sites, and transports of vitrified high-activity waste from reprocessing plants to the intermediate storage site (Gorleben). (orig.) [de

RISKIND: A computer program for calculating radiological consequences and health risks from transportation of spent nuclear fuel

Energy Technology Data Exchange (ETDEWEB)

Yuan, Y.C. [Square Y, Orchard Park, NY (United States); Chen, S.Y.; LePoire, D.J. [Argonne National Lab., IL (United States). Environmental Assessment and Information Sciences Div.; Rothman, R. [USDOE Idaho Field Office, Idaho Falls, ID (United States)

1993-02-01

This report presents the technical details of RISIUND, a computer code designed to estimate potential radiological consequences and health risks to individuals and the collective population from exposures associated with the transportation of spent nuclear fuel. RISKIND is a user-friendly, semiinteractive program that can be run on an IBM or equivalent personal computer. The program language is FORTRAN-77. Several models are included in RISKIND that have been tailored to calculate the exposure to individuals under various incident-free and accident conditions. The incidentfree models assess exposures from both gamma and neutron radiation and can account for different cask designs. The accident models include accidental release, atmospheric transport, and the environmental pathways of radionuclides from spent fuels; these models also assess health risks to individuals and the collective population. The models are supported by databases that are specific to spent nuclear fuels and include a radionudide inventory and dose conversion factors.

RISKIND: A computer program for calculating radiological consequences and health risks from transportation of spent nuclear fuel

International Nuclear Information System (INIS)

Yuan, Y.C.; Chen, S.Y.; LePoire, D.J.

1993-02-01

This report presents the technical details of RISIUND, a computer code designed to estimate potential radiological consequences and health risks to individuals and the collective population from exposures associated with the transportation of spent nuclear fuel. RISKIND is a user-friendly, semiinteractive program that can be run on an IBM or equivalent personal computer. The program language is FORTRAN-77. Several models are included in RISKIND that have been tailored to calculate the exposure to individuals under various incident-free and accident conditions. The incidentfree models assess exposures from both gamma and neutron radiation and can account for different cask designs. The accident models include accidental release, atmospheric transport, and the environmental pathways of radionuclides from spent fuels; these models also assess health risks to individuals and the collective population. The models are supported by databases that are specific to spent nuclear fuels and include a radionudide inventory and dose conversion factors

Assessment of radiological referral practice and effect of computer-based guidelines on radiological requests in two emergency departments

Energy Technology Data Exchange (ETDEWEB)

Carton, Matthieu; Auvert, Bertran; Guerini, Henri; Boulard, Jean-Christophe; Heautot, Jean-Francois; Landre, Marie-France; Beauchet, Alain; Sznajderi, Marc; Brun-Ney, Dominique; Chagnon, Sophie

2002-02-01

AIM: To assess medical emergency radiology referral practice compared with a set of French guidelines and to measure the efficiency of computer-based guidelines on unnecessary medical imaging. MATERIALS AND METHODS: All radiological requests were computerized in the medical emergency departments of two French teaching hospitals. During control periods, radiological requests were recorded but no action was taken. During intervention periods, reminder displays on screen indicated the appropriate recommendations. Three control and three intervention periods of 1 month each were conducted. The percentage of requests that did not conform to the guidelines and variation related to periods of control and intervention were measured. RESULTS: The proportion of requests that did not conform to the guidelines was 33{center_dot}2% when the guidelines were inactive and decreased to 26{center_dot}9% when the recommendations were active (P < 0{center_dot}0001). The three imaging examinations (chest radiographs, abdominal plain radiographs and CT of the brain) accounted for more than 80% of all requests; more than 50% of abdominal plain radiographs requests did not conform with recommendations while this percentage was respectively 24{center_dot}9% and 15{center_dot}8% for chest radiographs and computed tomography (CT) of the brain. Seven situations accounted for 70% of non-conforming radiological referrals; in these situations, junior practitioners' knowledge was inadequate. CONCLUSION: While the computer provided advice that was tailored to the needs of individual patients, concurrent with care, the effect of our intervention was weak. However, our study identified the few situations that were responsible for the majority of unnecessary radiological requests; we expect that this result could help clinicians and radiologists to develop more specific actions for these situations. Carton, M. et al. (2002). Clinical Radiology (2002)

Assessment of radiological referral practice and effect of computer-based guidelines on radiological requests in two emergency departments

International Nuclear Information System (INIS)

Carton, Matthieu; Auvert, Bertran; Guerini, Henri; Boulard, Jean-Christophe; Heautot, Jean-Francois; Landre, Marie-France; Beauchet, Alain; Sznajderi, Marc; Brun-Ney, Dominique; Chagnon, Sophie

2002-01-01

AIM: To assess medical emergency radiology referral practice compared with a set of French guidelines and to measure the efficiency of computer-based guidelines on unnecessary medical imaging. MATERIALS AND METHODS: All radiological requests were computerized in the medical emergency departments of two French teaching hospitals. During control periods, radiological requests were recorded but no action was taken. During intervention periods, reminder displays on screen indicated the appropriate recommendations. Three control and three intervention periods of 1 month each were conducted. The percentage of requests that did not conform to the guidelines and variation related to periods of control and intervention were measured. RESULTS: The proportion of requests that did not conform to the guidelines was 33·2% when the guidelines were inactive and decreased to 26·9% when the recommendations were active (P < 0·0001). The three imaging examinations (chest radiographs, abdominal plain radiographs and CT of the brain) accounted for more than 80% of all requests; more than 50% of abdominal plain radiographs requests did not conform with recommendations while this percentage was respectively 24·9% and 15·8% for chest radiographs and computed tomography (CT) of the brain. Seven situations accounted for 70% of non-conforming radiological referrals; in these situations, junior practitioners' knowledge was inadequate. CONCLUSION: While the computer provided advice that was tailored to the needs of individual patients, concurrent with care, the effect of our intervention was weak. However, our study identified the few situations that were responsible for the majority of unnecessary radiological requests; we expect that this result could help clinicians and radiologists to develop more specific actions for these situations. Carton, M. et al. (2002). Clinical Radiology (2002)

Challenges in Risk Assessment: Quantitative Risk Assessment

OpenAIRE

Jacxsens, Liesbeth; Uyttendaele, Mieke; De Meulenaer, Bruno

2016-01-01

The process of risk analysis consists out of three components, risk assessment, risk management and risk communication. These components are internationally well spread by Codex Alimentarius Commission as being the basis for setting science based standards, criteria on food safety hazards, e.g. setting maximum limits of mycotoxins in foodstuffs. However, the technical component risk assessment is hard to elaborate and to understand. Key in a risk assessment is the translation of biological or...

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)

Lateral sesamoid position in hallux valgus: correlation with the conventional radiological assessment.

Science.gov (United States)

Agrawal, Yuvraj; Desai, Aravind; Mehta, Jaysheel

2011-12-01

We aimed to quantify the severity of the hallux valgus based on the lateral sesamoid position and to establish a correlation of our simple assessment method with the conventional radiological assessments. We reviewed one hundred and twenty two dorso-plantar weight bearing radiographs of feet. The intermetatarsal and hallux valgus angles were measured by the conventional methods; and the position of lateral sesamoid in relation to first metatarsal neck was assessed by our new and simple method. Significant correlation was noted between intermetatarsal angle and lateral sesamoid position (Rho 0.74, p lateral sesamoid position and hallux valgus angle (Rho 0.56, p lateral sesamoid position is simple, less time consuming and has statistically significant correlation with that of the established conventional radiological measurements. Copyright © 2011 European Foot and Ankle Society. Published by Elsevier Ltd. All rights reserved.

Evaluation of the radiological risk resulting from road transportation of tritiated water

International Nuclear Information System (INIS)

Menossi, C.A.; Segado, R.; Reyes, R.

1983-01-01

A probability model for the evaluation of the individual radiological risk resulting from road transportation of tritiated water in 200-liter drums is presented. In order to evaluate such risk, an evaluation must be made of the probability for an individual to be involved in the consequences of a radiological transport accident, to incur a given dose and to suffer deleterious effects resulting from the dose incurred. With the purpose of quantifying the importance of accidents, a severity level classification was adopted as a function of the fraction of liquid volume spilled as a result of the accident. Considering the above-mentioned severity classification and the transported volume, the volume and the spill area are implied, while the soil characteristics are taken into account. By evaluating the spill characteristics, the average meteorological conditions in the area under analysis and the activity concentration of the transported liquid, the activity concentration values for tritium in air may be estimated, thus allowing calculation of the effective dose equivalent to be incurred by the individual who is most exposed to the consequences of an associated event. As a result of the summarized analysis above, a value of the individual risk per unit of activity concentration is obtained for tritium and for a given volume of transported liquid. 8 references

Evaluation and assessment methodology, standards, and procedures manual of the United States Federal Radiological Monitoring and Assessment Center

International Nuclear Information System (INIS)

Kerns, K.C.; Burson, Z.G.; Smith, J.M.; Blanchard, R.L.

2000-01-01

In the event of a major radiological emergency, the U.S. Federal Radiological Emergency Response Plan authorises the creation of the Federal Radiological Monitoring and Assessment Center (FRMAC). The FRMAC is established to co-ordinate the Federal off-site monitoring and assessment activities, and is comprised of representatives from several Federal agencies and Department of Energy contractors who provide assistance to the state(s) and Lead Federal Agency. The Evaluation and Assessment (E and A) Division of the FRMAC is responsible for receiving, storing, and interpreting environmental surveillance data to estimate the potential health consequences to the population in the vicinity of the accident site. The E and A Division has commissioned the preparation of a methodology and procedures manual which will result in a consistent approach by Division members in carrying out their duties. The first edition of this manual is nearing completion. In this paper, a brief review of the structure of the FRMAC is presented, with emphasis on the E and A Division. The contents of the E and A manual are briefly described, as are future plans for its expansion. (author)

Assessment of the radiological control at the IPEN radioisotope production facility

Energy Technology Data Exchange (ETDEWEB)

Carneiro, J.C.G.G.; Sanches, M.P.; Rodrigues, D.L.; Campos, D.; Nogueira, P.R.; Damatto, S.R.; Pecequilo, B.R.S. [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2015-07-01

The main objective of this work is to evaluate the 2013 annual radiological control results in the radiopharmaceuticals areas of the Nuclear and Energy Research Institute, IPEN/SP, Brazil and the environmental radiological impact, resulting from the practices there performed. The current evaluation was performed through the analysis of the results obtained from occupational and environmental monitoring with air samplers and TL dosimeters. All monitoring results were compared with the limits established by national standards. The radionuclides detected by air sampling (in activated carbon cartridges and filter paper) at the workplace during radioisotope production were {sup 131}I, {sup 99m}Tc and {sup 99}Mo, with activities concentrations values below the annual limits values. For the radioactive gaseous releases (Bq/m{sup 3} ), the activities concentrations also remained below the maximum admissible values, excepting to {sup 125}I release due to an unusual event occurred in a researcher laboratory, but the radiological impact to environmental was no significant. The occupational monitoring assessment was confirmed by the Environmental Radiological Monitoring Program results with air samplers and TL dosimeters. The mean annual background radiation at IPEN in 2013, according to the Environmental Radiological Monitoring Program results was 1.06 mSv. y{sup -1} , below the ICRP 103 recommended limit of 20 mSv.y{sup -1} for workers. (author)

Laenderyggens degeneration og radiologi

DEFF Research Database (Denmark)

Jacobsen, Steffen; Gosvig, Kasper Kjaerulf; Sonne-Holm, Stig

2006-01-01

Low back pain (LBP) is one of the most common conditions, and at the same time one of the most complex nosological entities. The lifetime prevalence is approximately 80%, and radiological features of lumbar degeneration are almost universal in adults. The individual risk factors for LBP and signi......Low back pain (LBP) is one of the most common conditions, and at the same time one of the most complex nosological entities. The lifetime prevalence is approximately 80%, and radiological features of lumbar degeneration are almost universal in adults. The individual risk factors for LBP...... and significant relationships between radiological findings and subjective symptoms have both been notoriously difficult to identify. The lack of consensus on clinical criteria and radiological definitions has hampered the undertaking of properly executed epidemiological studies. The natural history of LBP...

Development of Risk Assessment Methodology for State's Nuclear Security Regime

International Nuclear Information System (INIS)

Jang, Sung Soon; Seo, Hyung Min; Lee, Jung Ho; Kwak, Sung Woo

2011-01-01

Threats of nuclear terrorism are increasing after 9/11 terrorist attack. Treats include nuclear explosive device (NED) made by terrorist groups, radiological damage caused by a sabotage aiming nuclear facilities, and radiological dispersion device (RDD), which is also called 'dirty bomb'. In 9/11, Al Qaeda planed to cause radiological consequences by the crash of a nuclear power plant and the captured airplane. The evidence of a dirty bomb experiment was found in Afganistan by the UK intelligence agency. Thus, the international communities including the IAEA work substantial efforts. The leaders of 47 nations attended the 2010 nuclear security summit hosted by President Obama, while the next global nuclear summit will be held in Seoul, 2012. Most states established and are maintaining state's nuclear security regime because of the increasing threat and the international obligations. However, each state's nuclear security regime is different and depends on the state's environment. The methodology for the assessment of state's nuclear security regime is necessary to design and implement an efficient nuclear security regime, and to figure out weak points. The IAEA's INPRO project suggests a checklist method for State's nuclear security regime. The IAEA is now researching more quantitative methods cooperatively with several countries including Korea. In this abstract, methodologies to evaluate state's nuclear security regime by risk assessment are addressed

Comparison of models used for ecological risk assessment and human health risk assessment

International Nuclear Information System (INIS)

Ryti, R.T.; Gallegos, A.F.

1994-01-01

Models are used to derive action levels for site screening, or to estimate potential ecological or human health risks posed by potentially hazardous sites. At the Los Alamos National Laboratory (LANL), which is RCRA-regulated, the human-health screening action levels are based on hazardous constituents described in RCRA Subpart S and RESRAD-derived soil guidelines (based on 10 mRem/year) for radiological constituents. Also, an ecological risk screening model was developed for a former firing site, where the primary constituents include depleted uranium, beryllium and lead. Sites that fail the screening models are evaluated with site-specific human risk assessment (using RESRAD and other approaches) and a detailed ecological effect model (ECOTRAN). ECOTRAN is based on pharmacokinetics transport modeling within a multitrophic-level biological-growth dynamics model. ECOTRAN provides detailed temporal records of contaminant concentrations in biota, and annual averages of these body burdens are compared to equivalent site-specific runs of the RESRAD model. The results show that thoughtful interpretation of the results of these models must be applied before they can be used for evaluation of current risk posed by sites and the benefits of various remedial options. This presentation compares the concentrations of biological media in the RESRAD screening runs to the concentrations in ecological endpoints predicted by the ecological screening model. The assumptions and limitations of these screening models and the decision process where these are screening models are applied are discussed

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

Occuptional radiation exposures and thyroid cancer risk among radiologic technologists

Energy Technology Data Exchange (ETDEWEB)

Moon, Eun Kyeong; Lee, Won Jin [Korea University, Seoul (Korea, Republic of); Ha, Mina [Dankook University Seoul (Korea, Republic of); Kim, Jae Young [Keimyung University, Daegu (Korea, Republic of); Jun, Jae Kwan [National Cancer Center, Seoul (Korea, Republic of); Jin, Young Won [Korea Institute of Radiological and Medical Sciences, Seoul (Korea, Republic of)

2016-04-15

Medical radiation workers were among the earliest occupational groups exposed to external ionizing radiation due to their administration of a range of medical diagnostic procedures and accounted for 7.4 million worldwide in 2008. Ionizing radiation is the confirmed human carcinogen for most organ sites. The aims of the study is to evaluate the association between occupational practices including radiation exposure and thyroid cancer risk among radiologic technologists. We found no significant association between the risk of thyroid cancer and the majority of work practices among diagnostic radiation technologists in general. However workers performing fluoroscopy and interventional procedures showed increased risks although the lack of a clear exposure– response gradient makes it difficult to draw clear conclusions. Future studies with larger sample size and detailed work practices implementation are needed to clarify the role of occupational radiation work in thyroid cancer carcinogenesis.

Occuptional radiation exposures and thyroid cancer risk among radiologic technologists

International Nuclear Information System (INIS)

Moon, Eun Kyeong; Lee, Won Jin; Ha, Mina; Kim, Jae Young; Jun, Jae Kwan; Jin, Young Won

2016-01-01

Medical radiation workers were among the earliest occupational groups exposed to external ionizing radiation due to their administration of a range of medical diagnostic procedures and accounted for 7.4 million worldwide in 2008. Ionizing radiation is the confirmed human carcinogen for most organ sites. The aims of the study is to evaluate the association between occupational practices including radiation exposure and thyroid cancer risk among radiologic technologists. We found no significant association between the risk of thyroid cancer and the majority of work practices among diagnostic radiation technologists in general. However workers performing fluoroscopy and interventional procedures showed increased risks although the lack of a clear exposure– response gradient makes it difficult to draw clear conclusions. Future studies with larger sample size and detailed work practices implementation are needed to clarify the role of occupational radiation work in thyroid cancer carcinogenesis.

Methodology for and uses of a radiological source term assessment for potential impacts to stormwater and groundwater

International Nuclear Information System (INIS)

Teare, A.; Hansen, K.; DeWilde, J.; Yu, L.; Killey, D.

2001-01-01

A Radiological Source Term Assessment (RSTA) was conducted by Ontario Power Generation Inc. (OPG) at the Pickering Nuclear Generating Station (PNGS). Tritium had been identified in the groundwater at several locations under the station, and OPG initiated the RSTA as part of its ongoing efforts to improve operations and to identify potential sources of radionuclide impact to groundwater and stormwater at the station. The RSTA provides a systematic approach to collecting information and assessing environmental risk for radioactive contaminants based on a ranking system developed for the purpose. This paper provides an overview of the RSTA focusing on the investigative approach and how it was applied. This approach can find application at other generating stations. (author)

Instructional Vignettes in Publication and Journalism Ethics in Radiology Research: Assessment via a Survey of Radiology Trainees.

Science.gov (United States)

Rosenkrantz, Andrew B; Ginocchio, Luke A

2016-07-01

The aim of the present study was to assess the potential usefulness of written instructional vignettes relating to publication and journalism ethics in radiology via a survey of radiology trainees. A literature review was conducted to guide the development of vignettes, each describing a scenario relating to an ethical issue in research and publication, with subsequent commentary on the underlying ethical issue and potential approaches to its handling. Radiology trainees at a single institution were surveyed regarding the vignettes' perceived usefulness. A total of 21 vignettes were prepared, addressing institutional review board and human subjects protection, authorship issues, usage of previous work, manuscript review, and other miscellaneous topics. Of the solicited trainees, 24.7% (16/65) completed the survey. On average among the vignettes, 94.0% of the participants found the vignette helpful; 19.9 received prior formal instruction on the issue during medical training; 40.0% received prior informal guidance from a research mentor; and 42.0% indicated that the issue had arisen in their own or a peer's prior research experience. The most common previously experienced specific issue was authorship order (93.8%). Free-text responses were largely favorable regarding the value of the vignettes, although also indicated numerous challenges in properly handling the ethical issues: impact of hierarchy, pressure to publish, internal politics, reluctance to conduct sensitive conversations with colleagues, and variability in journal and professional society policies. Radiology trainees overall found the vignettes helpful, addressing commonly encountered topics for which formal and informal guidance were otherwise lacking. The vignettes are publicly available through the Association of University Radiologists (AUR) website and may foster greater insights by investigators into ethical aspects of the publication and journalism process, thus contributing to higher quality

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

RADIOLOGY EDUCATION: A PILOT STUDY TO ASSESS KNOWLEDGE OF MEDICAL STUDENTS REGARDING IMAGING IN TRAUMA.

Science.gov (United States)

Siddiqui, Saad; Saeed, Muhammad Anwar; Shah, Noreen; Nadeem, Naila

2015-01-01

Trauma remains one of the most frequent presentations in emergency departments. Imaging has established role in setting of acute trauma with ability to identify potentially fatal conditions. Adequate knowledge of health professionals regarding trauma imaging is vital for improved healthcare. In this work we try to assess knowledge of medical students regarding imaging in trauma as well as identify most effective way of imparting radiology education. This cross-sectional pilot study was conducted at Aga Khan University Medical College & Khyber Girls Medical College, to assess knowledge of medical students regarding imaging protocols practiced in initial management of trauma patients. Only 40 & 20% respectively were able to identify radiographs included in trauma series. Very few had knowledge of correct indication for Focused abdominal sonography in trauma. Clinical radiology rotation was reported as best way of learning radiology. Change in curricula & restructuring of clinical radiology rotation structure is needed to improve knowledge regarding Trauma imaging.

Escalation of terrorism? On the risk of attacks with chemical, biological, radiological and nuclear weapons or materials

International Nuclear Information System (INIS)

Nass, Jens

2010-01-01

The report on the risk of attacks with chemical, biological, radiological and nuclear weapons or materials covers the following topics: the variety of terrorism: ethnic-nationalistic, politically motivated, social revolutionary, political extremism, religious fanaticism, governmental terrorism; CBRN (chemical, biological, radiological, nuclear) weapons and materials: their availability and effectiveness in case of use; potential actor groups; prevention and counter measures, emergency and mitigating measures.

Radiographers' and radiology practitioners' opinion, experience and practice of benefit-risk communication and consent in paediatric imaging

International Nuclear Information System (INIS)

Portelli, J.L.; McNulty, J.P.; Bezzina, P.; Rainford, L.

2016-01-01

Objectives: To investigate radiographers' and radiology practitioners' opinion, experience and practice of radiation benefit-risk communication and consent for paediatric imaging examinations. Methods: A cross-sectional survey was conducted amongst radiographers and radiology practitioners working at a primary paediatric referral centre in Malta, so as to acquire information about their interactions with paediatric patients and/or their parents, particularly their opinion and practice of communicating benefit-risk information and seeking consent for imaging examinations. Results: The return of 112 questionnaires provided a response rate of 66.7%. Findings revealed varied practice relating to the provision of benefit-risk information, whereby details concerning examination benefits and potential risks are not always conveyed. For 89% of participants, parental consent was sought for paediatric imaging examinations in their current practice. Only 36.7% of participants indicated that they were highly confident in their ability to communicate benefit-risk information. The study findings also revealed that parents can truly be worried about the associated radiation exposure, with some even refusing an imaging examination as a result of such concerns. Conclusions: The practice of communicating benefit-risk information to paediatric patients and/or their parents is varied. A possible gap in benefit-risk communication education and/or training was identified, which may impact radiographers' and radiology practitioners' confidence in conveying such information. Education/training activities for radiographers and radiology practitioners are therefore necessary to foster improved benefit-risk dialogues and help provide reassurance to parents/guardians about the benefits of appropriately indicated paediatric imaging examinations. - Highlights: • The practice of communicating radiation benefit-risk information to parents of paediatric patients is varied. �

Radiological impact of natural radioactivity in Egyptian phosphate rocks, phosphogypsum and phosphate fertilizers

International Nuclear Information System (INIS)

El-Bahi, S.M.; Sroor, A.; Mohamed, Gehan Y.; El-Gendy, N.S.

2017-01-01

In this study, the activity concentrations of the natural radionuclides in phosphate rocks and its products were measured using a high- purity germanium detector (HPGe). The obtained activity results show remarkable wide variation in the radioactive contents for the different phosphate samples. The average activity concentration of "2"3"5U, "2"3"8U, "2"2"6Ra, "2"3"2Th and "4"0K was found as (45, 1031, 786, 85 and 765 Bq/kg) for phosphate rocks, (28, 1234, 457, 123 and 819 Bq/kg) for phosphate fertilizers, (47, 663, 550, 79 and 870 Bq/kg) for phosphogypsum and (25, 543, 409, 54 and 897 Bq/kg) for single super phosphate respectively. Based on the measured activities, the radiological parameters (activity concentration index, absorbed gamma dose rate in outdoor and indoor and the corresponding annual effective dose rates and total excess lifetime cancer risk) were estimated to assess the radiological hazards. The total excess lifetime cancer risk (ELCR) has been calculated and found to be high in all samples, which related to high radioactivity, representing radiological risk for the health of the population. - Highlights: • Level of radioactivity of phosphate rocks and by-products samples. • The radiological health hazard parameters. • Radiological risk to the health of the population. • The excess lifetime cancer risk factor.

Planning new basic guideline to the radiological risk. Content, radiological criteria and implementation

International Nuclear Information System (INIS)

Calvin Cuartero, M.; Vega Riber, R. de la; Martin Calvarro, J. M.

2011-01-01

The most important aspects of the Basic Guideline focus on their area of planning, groups of potential radiological emergencies in the type of activity associated with the levels of response planning and responsible organizations, structure and functions for each level, radiological criteria, implementation and maintenance of the effectiveness of the level of response plans abroad.

Preoperative radiological assessment of children with pectus excavatum

International Nuclear Information System (INIS)

Kilda, A.; Barauskas, V.; Basevicius, A.; Lukosevicius, S.

2005-01-01

Objective: The degree of the pediatric chest deformation that should be subjected to corrective surgical treatment or conservative treatment remains poorly defined as recognized. In the present study, using preoperative and postoperative radiological examination data, we aim to assess what degree of chest wall deformation changes statistically reliably after surgery. Materials and methods: Radiological chest examinations were performed for 88 children before and after remedial operations. Chest X-ray and CT scans were done to measure transversal chest width; sagittal left chest side depth, sagittal right chest side depth, sternovertebral distance, and vertebral body length. Derivative indices were also estimated: the Vertebral Index, the Frontosagittal Index, the Haller index, and the asymmetry index. Computerized assessment of data was used. For statistical analysis, the software 'STATISTICA 6.0' was used. Results: Postoperatively, the Vertebral Index increased approximately by 2.37±2.72; the Frontosagittal Index decreased by 4.60±4.34, and the Haller index value increased approximately up by 0.45±0.49. Statistically reliable deformation index difference before and after surgery was not detected when the Vertebral Index was below 26.2, p=0.08; the Frontosagittal Index was above 32.9, p=0.079; and the Haller Index was less than 3.12, p=0.098. Conclusions: Preoperative CT scanning, coupled with assessment of the chest wall shape and the deformation degree, would be necessary for pediatric patients. The following deformation indices are indications for surgical treatment: VI > 26, FSI 3.1. (author)

Radiological protection and public health: crossbreeding

International Nuclear Information System (INIS)

Smeesters, Patrick; Pinak, Miroslav

2008-01-01

Full text: This paper summarizes the scope of activities, ongoing experience and current results of the Expert Group on the Public Health Perspective in Radiological Protection (EGPH) of the Committee of Radiological Protection and Public Health, OECD Nuclear Energy Agency. While the prime and general task of the EGPH group is looking at how the public health and radiation protection can better take an advantage of their respective perspectives, the following four areas have been explored in detail: a) Exposure to radon; b) Justification of medical exposures; c) Public health judgement and decision making based on new scientific evidence; and d) Management of individual differences. In most of these areas, a targeted telephone survey on public policies in selected countries was used for collecting information from stake holders (public, consumers groups, public health and radiation protection regulators, governmental bodies, medical practitioners, patients, scientific communities, NGOs, etc.). The presented paper also highlights key issues of collected information and summarises existing approaches and policies. The case study on exposure to radon collects national information on approaches to the management of domestic radon risks, focusing on the integration of radiation protection and public health aspects (quality of dwellings, overall quality of indoor air, perception of radon levels, position of radon risk in the pool of other risks). In the case of justification of medical exposures, the Group studies the applications of the justification principle in opportunistic screenings (responsibilities, management of the situation, risk assessment). The precautionary principle and its impact on policy judgement in the light of significant scientific uncertainties can have a large influence on radiological-protection decision making. The case study on public health judgement and decision making based on new scientific evidence is exploring how these uncertainties and

Non-nuclear radiological emergencies. Special plan for radiological risk of the Valencian Community

International Nuclear Information System (INIS)

Rodríguez Rodrigo, I.; Piles Alepuz, I.; Peiró Juan, J.; Calvet Rodríguez, D.

2015-01-01

After the publication of the Radiological Hazard Basic Directive, Generalitat (the regional government in Valencian Community) initiated the edition of the pertinent Special Plan, with the objective to assemble the response of all the Security and Emergency Agencies, including the Armed Forces, in a radiological emergency affecting the territory of the Valencian Community, under a single hierarchy command. Being approved and homologated the Radiological Hazard Special Plan, Generalitat has undertaken the implementation process planned to finish in June 2015. Following the same process as other Plans, implementation is organized in a first informative stage, followed of a formative and training stage, and finishing with an activation exercise of the Plan. At the end of the process, is expected that every Agency will know their functions, the structure and organization in which the intervention takes place, the resources needed, and adapt their protocols to the Plan requirements. From the beginning, it has been essential working together with the Nuclear Safety Council, as is established in the agreement signed in order to collaborate in Planning, Preparedness and Response in Radiological Emergencies. [es

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

Radiological optimization

International Nuclear Information System (INIS)

Zeevaert, T.

1998-01-01

Radiological optimization is one of the basic principles in each radiation-protection system and it is a basic requirement in the safety standards for radiation protection in the European Communities. The objectives of the research, performed in this field at the Belgian Nuclear Research Centre SCK-CEN, are: (1) to implement the ALARA principles in activities with radiological consequences; (2) to develop methodologies for optimization techniques in decision-aiding; (3) to optimize radiological assessment models by validation and intercomparison; (4) to improve methods to assess in real time the radiological hazards in the environment in case of an accident; (5) to develop methods and programmes to assist decision-makers during a nuclear emergency; (6) to support the policy of radioactive waste management authorities in the field of radiation protection; (7) to investigate existing software programmes in the domain of multi criteria analysis. The main achievements for 1997 are given

Evaluation criteria for emergency response plans in radiological transportation

International Nuclear Information System (INIS)

Lindell, M.K.; Perry, R.W.

1980-01-01

This paper identifies a set of general criteria which can be used as guides for evaluating emergency response plans prepared in connection with the transportation of radiological materials. The development of criteria takes the form of examining the meaning and role of emergency plans in general, reviewing the process as it is used in connection with natural disasters and other nonnuclear disasters, and explicitly considering unique aspects of the radiological transportation setting. Eight areas of critical importance for such response plans are isolated: notification procedures; accident assessment; public information; protection of the public at risk; other protective responses; radiological exposure control; responsibility for planning and operations; and emergency response training and exercises. (Auth.)

The radiologic quality of water supply in France, 2005-2007

International Nuclear Information System (INIS)

2009-01-01

This report, while proposing many graphs, tables and maps, firstly describes the context of water radioactivity (definition, origin, population exposure, water radiologic quality indicators, uranium in water) and then the methodology of the regional sanitary controls, of the national survey on radiologic quality of tap water, and the radionuclide analyses (notably uranium isotopes) from which these data are obtained. Results and data from these controls, survey and analyses are then presented and discussed. The authors highlight the fact that some results must be cautiously interpreted as they may depend on sampling and analysis modalities, and on the sanitary control frequency. They also assess the chemical and radiological risk associated to uranium

Evaluation of excess lifetime cancer risk and radiological hazard in produced water from some flow stations in Delta State, Nigeria

International Nuclear Information System (INIS)

Avwiri, G. O.; Esi, E. O.

2014-01-01

The radiological effects and excess lifetime cancer risk of produced water collected from seven oil and gas flow stations (fields onshore) of Delta State, Nigeria were estimated using standard analytical. Twenty- one produced water samples from seven flow stations waste pit were collected within the oil fields using standard methods. The radionuclide concentrations in the produced water samples were measured using gamma spectroscopy method. The average values obtained for representative gamma index, annual effective dose equivalent (outdoor), annual effective dose equivalent (indoor) are 0.104mSv/y, 0.0229mSv/y and 0.03276mSv/y respectively when compared with standard of 1.0mSv/y are all below unity. Excess lifetime cancer risk obtained values ranged from 0.0196mSv/y - 0.0434mSv/y with a mean value of 0.0288mSv/y. When compared with the world average standard (0.29 x 10 -3 ), it was observed that the obtained values are higher than the world allowable average. The absorbed dose rate ranged from 4.570mSv/y to 10.088mSv/y with average value of 6.68mSvy-1 was found to be higher than the UNSCEAR 2000 acceptable standard of 1.5mSvy -1 . The results obtained in this study provides a baseline map of radiological effect and excess lifetime cancer risk levels in the Niger Delta environment and will be used as reference information to assess any changes in this studied area. This subject is important in environmental radiological protection, since produced water are widely been discharged in the environment during oil and gas productions.

Dealing with at-risk populations in radiological/nuclear emergencies

International Nuclear Information System (INIS)

Wilkinson, D.

2009-01-01

In a mass casualty event, there will be at-risk populations that will require unique triage, treatment and consequence management to minimise immediate and long-term health effects. This statement is particularly true for radiological/nuclear (R/N) disasters where individuals exhibit a broad range of physiological responses to radiation exposure. For example, immunocompromised individuals will experience more detrimental radiation health effects; however, it is not always possible to definitively identify these individuals at the time of triage. Immediate and long-term consequence management for these individuals may require unique and potentially limited resources. Thus, at the time of an R/N event, it is crucial to assist community planners by: (a) rapidly identifying at-risk individuals who may have been exposed; (b) determining the dose and individual-specific health risks associated with radiation exposure; (c) identifying additional resources needed to deal with unique, population-specific requirements; and (d) developing treatment strategies in keeping with the rules of 'supply and demand'. A comprehensive approach to identifying issues relevant to the R/N emergency preparedness for dealing with at-risk populations will be discussed with the aim of defining future research objectives. (authors)

The Importance of Curriculum-Based Training and Assessment in Interventional Radiology

Energy Technology Data Exchange (ETDEWEB)

Belli, Anna-Maria, E-mail: anna.belli@stgeorges.nhs.uk [St. George’s Hospital, Department of Radiology (United Kingdom); Reekers, Jim A., E-mail: j.a.reekers@amc.uva.nl [Academic Medical Centre, Department of Radiology (Netherlands); Lee, Michael, E-mail: mlee@rcsi.ie [Beaumont Hospital, Department of Radiology (Ireland)

2013-10-30

Physician performance and outcomes are being scrutinised by health care providers to improve patient safety and cost efficiency. Patients are best served by physicians who have undergone appropriate specialist training and assessment and perform large numbers of cases to maintain their skills. The Cardiovascular and Interventional Radiological Society of Europe has put into place a curriculum for training in interventional radiology (IR) and a syllabus with an examination, the European Board of Interventional Radiology, providing evidence of attainment of an appropriate and satisfactory skill set for the safe practice of IR. This curriculum is appropriate for IR where there is a high volume of image-guided procedures in vascular and nonvascular organ systems with cross-use of minimally invasive techniques in patients with a variety of disease processes. Other specialties may require different, longer, and more focused training if their experience is “diluted” by the need to master a different skill set.

The Importance of Curriculum-Based Training and Assessment in Interventional Radiology

International Nuclear Information System (INIS)

Belli, Anna-Maria; Reekers, Jim A.; Lee, Michael

2014-01-01

Physician performance and outcomes are being scrutinised by health care providers to improve patient safety and cost efficiency. Patients are best served by physicians who have undergone appropriate specialist training and assessment and perform large numbers of cases to maintain their skills. The Cardiovascular and Interventional Radiological Society of Europe has put into place a curriculum for training in interventional radiology (IR) and a syllabus with an examination, the European Board of Interventional Radiology, providing evidence of attainment of an appropriate and satisfactory skill set for the safe practice of IR. This curriculum is appropriate for IR where there is a high volume of image-guided procedures in vascular and nonvascular organ systems with cross-use of minimally invasive techniques in patients with a variety of disease processes. Other specialties may require different, longer, and more focused training if their experience is “diluted” by the need to master a different skill set

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.)

Practical Implications for an Effective Radiology Residency Quality Improvement Program for Milestone Assessment.

Science.gov (United States)

Leddy, Rebecca; Lewis, Madelene; Ackerman, Susan; Hill, Jeanne; Thacker, Paul; Matheus, Maria; Tipnis, Sameer; Gordon, Leonie

2017-01-01

Utilization of a radiology resident-specific quality improvement (QI) program and curriculum based on the Accreditation Council for Graduate Medical Education (ACGME) milestones can enable a program's assessment of the systems-based practice component and prepare residents for QI implementation post graduation. This article outlines the development process, curriculum, QI committee formation, and resident QI project requirements of one institution's designated radiology resident QI program. A method of mapping the curriculum to the ACGME milestones and assessment of resident competence by postgraduate year level is provided. Sample projects, challenges to success, and lessons learned are also described. Survey data of current trainees and alumni about the program reveal that the majority of residents and alumni responders valued the QI curriculum and felt comfortable with principles and understanding of QI. The most highly valued aspect of the program was the utilization of a resident education committee. The majority of alumni responders felt the residency quality curriculum improved understanding of QI, assisted with preparation for the American Board of Radiology examination, and prepared them for QI in their careers. In addition to the survey results, outcomes of resident project completion and resident scholarly activity in QI are evidence of the success of this program. It is hoped that this description of our experiences with a radiology resident QI program, in accordance with the ACGME milestones, may facilitate the development of successful QI programs in other diagnostic radiology residencies. Copyright © 2017 The Association of University Radiologists. Published by Elsevier Inc. All rights reserved.

Development of Integrated Code for Risk Assessment (INCORIA) for Physical Protection System

International Nuclear Information System (INIS)

Jang, Sung Soon; Seo, Hyung Min; Yoo, Ho Sik

2010-01-01

A physical protection system (PPS) integrates people, procedures and equipment for the protection of assets or facilities against theft, sabotage or other malevolent human attacks. Among critical facilities, nuclear facilities and nuclear weapon sites require the highest level of PPS. After the September 11, 2001 terrorist attacks, international communities, including the IAEA, have made substantial efforts to protect nuclear material and nuclear facilities. The international flow on nuclear security is using the concept or risk assessment. The concept of risk assessment is firstly devised by nuclear safety people. They considered nuclear safety including its possible risk, which is the frequency of failure and possible consequence. Nuclear security people also considers security risk, which is the frequency of threat action, vulnerability, and consequences. The concept means that we should protect more when the credible threat exists and the possible radiological consequence is high. Even if there are several risk assessment methods of nuclear security, the application needs the help of tools because of a lot of calculation. It's also hard to find tools for whole phase of risk assessment. Several codes exist for the part of risk assessment. SAVI are used for vulnerability of PPS. Vital area identification code is used for consequence analysis. We are developing Integrated Code for Risk Assessment (INCORIA) to apply risk assessment methods for nuclear facilities. INCORIA evaluates PP-KINAC measures and generation tools for threat scenario. PP-KINAC is risk assessment measures for physical protection system developed by Hosik Yoo and is easy to apply. A threat scenario tool is used to generate threat scenario, which is used as one of input value to PP-KINAC measures

Assessing scenario and parametric uncertainties in risk analysis: a model uncertainty audit

International Nuclear Information System (INIS)

Tarantola, S.; Saltelli, A.; Draper, D.

1999-01-01

In the present study a process of model audit is addressed on a computational model used for predicting maximum radiological doses to humans in the field of nuclear waste disposal. Global uncertainty and sensitivity analyses are employed to assess output uncertainty and to quantify the contribution of parametric and scenario uncertainties to the model output. These tools are of fundamental importance for risk analysis and decision making purposes

Medical irradiation risk assessment based on the data of radiation-hygienic passportization in the regions of the Russian Federation

Directory of Open Access Journals (Sweden)

V. Ju. Golikov

2015-01-01

Full Text Available This article is aimed at methodology development for collective risk assessment of medical irradiation, basing on results of radiation-hygienic passportization in the Russian Federation regions, i.e. using values of collective effective doses for big groups of medical technologies: photoroentgenography, roentgenography, roentgenoscopy, and computer tomography. Use of the effective dose concept for medical irradiation risk definition involves a number of essential restrictions. Age and sex of the employees and of general population (effective dose concept has been developed for these groups of people may essentially differ from those in patients. Lifelong risk of stochastic effects occurrence in children is 2-3 times higher than the rating values used in effective dose concept, while for elderly people (about 60 years at irradiation time it’s 4-5 times lower. The article suggests the algorithm of effective doses values correcting factors assessment for consideration of dependence of radiogenic cancer risk factors on age and sex. This enables to assess more correctly collective risk of radiology and nuclear medicine imaging. Since patients tend to be elderly and their risk factor is below the rating used in the effective dose concept, the values of these correcting factors for most radiology and nuclear medicine imaging are below one. Thus, in most cases, the effective dose concept leads to conservative assessment of medical irradiation collective risk.

Radiological impact of oil/gas industry

International Nuclear Information System (INIS)

Botezatu, E.; Grecea, C.

2006-01-01

The objective of this study was to assess the radiological impact on the environment and population of the oil/gas industry that is non-nuclear industry but uses and can produce materials, with an enhanced content of naturally occurring radionuclides. The natural radioactivity levels in the oil field environmental media, which could represent a risk for the people living in the areas influenced by this non-nuclear industry, do not indicate an increase in the natural radiation background. From a radiological point of view, the situation does not pose any immediate concern. Some places however need further investigations, with special emphasis on the control of 226 Ra releases to prevent from polluting the environment with this radionuclide. The growing concern amongst the population about the quality of their environment increases the significance of impact assessment of radioactive releases into the environment even if natural radionuclides occur. (N.C.)

Radiological health assessment of natural radioactivity in the vicinity of Obajana cement factory, North Central Nigeria

Directory of Open Access Journals (Sweden)

Omoniyi Matthew Isinkaye

2015-01-01

Full Text Available Measurements of activity concentrations of natural radionuclides in and around Obajana cement factory, North Central Nigeria have been carried out in this study to determine the activity levels of natural radionuclides in different environmental matrices in order to assess the radiological health hazards associated with the use of these matrices by the local population. A low-background Pb-shielded gamma spectroscopic counting assembly utilizing NaI (Tl detector was employed for the measurements. The results show that sediment samples have the highest activity concentrations of all the radionuclides relative to soil, farmland soil, and rock samples. The radium equivalent activity and indoor gamma dose rates together with the corresponding annual effective indoor doses evaluated were found to be lower than their permissible limits. It suffices to say, that contrary to age-long fear of radiation risks to the population in the vicinity of the cement factory, no excessive radiological health hazards either indoors and/or outdoors is envisaged. Therefore, the environmental matrices around the factory could be used without any restrictions.

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

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)

ANDROS: A code for Assessment of Nuclide Doses and Risks with Option Selection

International Nuclear Information System (INIS)

Begovich, C.L.; Sjoreen, A.L.; Ohr, S.Y.; Chester, R.O.

1986-11-01

ANDROS (Assessment of Nuclide Doses and Risks with Option Selection) is a computer code written to compute doses and health effects from atmospheric releases of radionuclides. ANDROS has been designed as an integral part of the CRRIS (Computerized Radiological Risk Investigation System). ANDROS reads air concentrations and environmental concentrations of radionuclides to produce tables of specified doses and health effects to selected organs via selected pathways (e.g., ingestion or air immersion). The calculation may be done for an individual at a specific location or for the population of the whole assessment grid. The user may request tables of specific effects for every assessment grid location. Along with the radionuclide concentrations, the code requires radionuclide decay data, dose and risk factors, and location-specific data, all of which are available within the CRRIS. This document is a user manual for ANDROS and presents the methodology used in this code

Radiological assessment of 50 cases of incisive or maxillary neoplasia in the dog

International Nuclear Information System (INIS)

Frew, D.G.; Dobson, J.M.

1992-01-01

This paper reviews the radiological features of 50 canine incisive or maxillary tumours and discusses the value of radiological assessment in the diagnosis and staging of these tumours. The 50 tumours examined included 21 sarcomas, 15 carcinomas, three melanomas and an assortment of benign tumours of the oral cavity. There was not any site specificity for the different histological tumour types within the upper dental arcade, although fibrosarcomas had a tendency to be maxillary whereas the squamous cell carcinomas were equally distributed between the incisive and maxillary regions. Seventy-eight per cent of fibrosarcomas, 82 per cent of squamous cell carcinoma and all three melanomas examined showed radiological evidence of bone involvement. Radiographic changes were also seen in the benign tumours. The pattern of growth of tumours correlated with the radiological changes observed. Malignant tumours showed a tendency to irregular or aggressive bone loss whereas bone production predominated in the benign tumours

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

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

The reliability and validity of radiological assessment for patellar instability. A systematic review and meta-analysis

Energy Technology Data Exchange (ETDEWEB)

Smith, Toby O. [University of East Anglia, Faculty of Health, Norwich (United Kingdom); Davies, Leigh [Norfolk and Norwich University Hospital, Norwich (United Kingdom); Toms, Andoni P.; Donell, Simon T. [University of East Anglia, Faculty of Health, Norwich (United Kingdom); Norfolk and Norwich University Hospital, Norwich (United Kingdom); Hing, Caroline B. [St George' s Hospital, London (United Kingdom)

2011-04-15

To determine the discriminative validity and reliability of the evidence base using meta-analysis. A review of published sources using the databases AMED, CINHAL, EMBASE, MEDLINE, Scopus and the Cochrane Library, and for unpublished material was conducted. All studies assessing the reliability, validity, sensitivity or specificity of magnetic resonance imaging (MRI), computed tomography (CT) or ultrasound (US) of the patellofemoral joint of patients following patellar dislocation, subluxation or instability, were included. A meta-analysis was performed to assess the difference in radiological measurements between healthy controls and subjects with patellar instability in order to assess discrimination validity. A narrative assessment was used to evaluate the inter- and intra-observer reliability as well as the sensitivity and specificity of specific radiological measurements. A total of 27 studies were reviewed. The findings indicated that there was acceptable inter-observer and intra-observer reliability and validity for different methods of assessing patellar height and the sulcus angle with X-ray, MRI and CT methods, and the tibial tubercle-trochlear groove (TT-TG) assessed using CT. There was poor reliability or validity for the assessment of severity of trochlear dysplasia and the sulcus angle using US. There is insufficient evidence to determine the reliability, validity, sensitivity or specificity of tests such as the congruence angle, lateral patellar displacement, lateral patellar tilt, trochlear depth, boss height, the crossing sign or Wiberg patellar classification. A critical appraisal of the literature identified a number of recurrent methodological limitations. Further study is recommended to evaluate the reliability and validity of these radiological outcomes using well-designed radiological trials. (orig.)

The reliability and validity of radiological assessment for patellar instability. A systematic review and meta-analysis

International Nuclear Information System (INIS)

Smith, Toby O.; Davies, Leigh; Toms, Andoni P.; Donell, Simon T.; Hing, Caroline B.

2011-01-01

To determine the discriminative validity and reliability of the evidence base using meta-analysis. A review of published sources using the databases AMED, CINHAL, EMBASE, MEDLINE, Scopus and the Cochrane Library, and for unpublished material was conducted. All studies assessing the reliability, validity, sensitivity or specificity of magnetic resonance imaging (MRI), computed tomography (CT) or ultrasound (US) of the patellofemoral joint of patients following patellar dislocation, subluxation or instability, were included. A meta-analysis was performed to assess the difference in radiological measurements between healthy controls and subjects with patellar instability in order to assess discrimination validity. A narrative assessment was used to evaluate the inter- and intra-observer reliability as well as the sensitivity and specificity of specific radiological measurements. A total of 27 studies were reviewed. The findings indicated that there was acceptable inter-observer and intra-observer reliability and validity for different methods of assessing patellar height and the sulcus angle with X-ray, MRI and CT methods, and the tibial tubercle-trochlear groove (TT-TG) assessed using CT. There was poor reliability or validity for the assessment of severity of trochlear dysplasia and the sulcus angle using US. There is insufficient evidence to determine the reliability, validity, sensitivity or specificity of tests such as the congruence angle, lateral patellar displacement, lateral patellar tilt, trochlear depth, boss height, the crossing sign or Wiberg patellar classification. A critical appraisal of the literature identified a number of recurrent methodological limitations. Further study is recommended to evaluate the reliability and validity of these radiological outcomes using well-designed radiological trials. (orig.)

Malpractice claims in interventional radiology: frequency, characteristics and protective measures.

Science.gov (United States)

Magnavita, N; Fileni, A; Mirk, P; Magnavita, G; Ricci, S; Cotroneo, A R

2013-04-01

The use of interventional radiology procedures has considerably increased in recent years, as has the number of related medicolegal litigations. This study aimed to highlight the problems underlying malpractice claims in interventional radiology and to assess the importance of the informed consent process. The authors examined all insurance claims relating to presumed errors in interventional radiology filed by radiologists over a period of 14 years after isolating them from the insurance database of all radiologists registered with the Italian Society of Medical Radiology (SIRM) between 1 January1993 and 31 December 2006. In the period considered, 98 malpractice claims were filed against radiologists who had performed interventional radiology procedures. In 21 cases (21.4%), the event had caused the patient's death. In >80% of cases, the event occurred in a public facility. The risk of a malpractice claim for a radiologist practising interventional procedures is 47 per 1,000, which corresponds to one malpractice claim for each 231 years of activity. Interventional radiology, a discipline with a biological risk profile similar to that of surgery, exposes practitioners to a high risk of medicolegal litigation both because of problems intrinsic to the techniques used and because of the need to operate on severely ill patients with compromised clinical status. Litigation prevention largely depends on both reducing the rate of medical error and providing the patient with correct and coherent information. Adopting good radiological practices, scrupulous review of procedures and efficiency of the instruments used and audit of organisational and management processes are all factors that can help reduce the likelihood of error. Improving communication techniques while safeguarding the patient's right to autonomy also implies adopting clear and rigorous processes for obtaining the patient's informed consent to the medical procedure.

Fifty years of radiological protection

International Nuclear Information System (INIS)

2007-01-01

On 21 March 1957, the Steering Committee for Nuclear Energy of the Organisation for European Economic Co-operation established the Working Party on Public Health and Safety. From this early date onwards, radiological protection formed a central part of the work of what was to become the OECD Nuclear Energy Agency. Now, 50 years later, the Committee on Radiation Protection and Public Health (CRPPH) has commissioned this historical review of half a century of work and accomplishments. Over this period, the key topics in radiological protection have been identified, debated and addressed by the CRPPH. This report brings this history to life, presenting the major questions in the context of their time, and of the personalities who worked to address them. The developments and views of the past condition how we are able to assess and manage radiological risks today, as well as how we may adjust to challenges that will or could emerge in the coming years. This heritage is thus an important element for the CRPPH to consider as it looks forward to its next 50 years of accomplishments. (author)

Ethical and social implications of microdosing clinical trial (3). Radiological protection of human subjects in research

International Nuclear Information System (INIS)

Kurihara, Chieko

2008-01-01

Internal irradiation of human subjects in research is discussed. Radiological protection of human subjects in medical research in a framework of radiation protection is surveyed from a viewpoint of general life-ethics and research-ethics. A workshop 'On the internal irradiation of human subjects' to summarize special and systematic knowledge was organized by Research Center for Radiation Protection, National Institute of Radiological Sciences in the beginning of 2008. Activities of this workshop are introduced. Discussion covers also (1) Research ethics and radiation protection, (2) Fundamentals and applications of risk-benefit assessment, (3) Human subjects risk assessment in ICRP recommendation, (4) Mechanism of human subjects internal irradiation assessment, and (5) Present status and future prospects in Japan. (K.Y.)

Alternative Metrics ("Altmetrics") for Assessing Article Impact in Popular General Radiology Journals.

Science.gov (United States)

Rosenkrantz, Andrew B; Ayoola, Abimbola; Singh, Kush; Duszak, Richard

2017-07-01

Emerging alternative metrics leverage social media and other online platforms to provide immediate measures of biomedical articles' reach among diverse public audiences. We aimed to compare traditional citation and alternative impact metrics for articles in popular general radiology journals. All 892 original investigations published in 2013 issues of Academic Radiology, American Journal of Roentgenology, Journal of the American College of Radiology, and Radiology were included. Each article's content was classified as imaging vs nonimaging. Traditional journal citations to articles were obtained from Web of Science. Each article's Altmetric Attention Score (Altmetric), representing weighted mentions across a variety of online platforms, was obtained from Altmetric.com. Statistical assessment included the McNemar test, the Mann-Whitney test, and the Pearson correlation. Mean and median traditional citation counts were 10.7 ± 15.4 and 5 vs 3.3 ± 13.3 and 0 for Altmetric. Among all articles, 96.4% had ≥1 traditional citation vs 41.8% for Altmetric (P nonimaging content (11.5 ± 16.2 vs 6.9 ± 9.8, P nonimaging content (5.1 ± 11.1 vs 2.8 ± 13.7, P = 0.006). Although overall online attention to radiology journal content was low, alternative metrics exhibited unique trends, particularly for nonclinical articles, and may provide a complementary measure of radiology research impact compared to traditional citation counts. Copyright © 2017 The Association of University Radiologists. Published by Elsevier Inc. All rights reserved.

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

WHO's health risk assessment of extremely low frequency electric fields

International Nuclear Information System (INIS)

Repacholi, M.H.

2003-01-01

The World Health Organization (WHO), the International Commission on Non-Ionizing Radiation Protection (ICNIRP), WHOs scientific collaborating centres (including the UKs National Radiological Protection Board (NRPB) and over 50 participating Member States are participants of WHOs International EMF Project. As part of WHOs health risk assessment process for extremely low frequency fields (ELFs), this workshop was convened by NRPB to assist WHO in evaluating potential health impacts of electrical currents and fields induced by ELF in molecules, cells, tissues and organs of the body. This paper describes the process by which WHO will conduct its health risk assessment. WHO is also trying to provide information on why exposure to ELF magnetic fields seems to be associated with an increased incidence of childhood leukaemia. Are there mechanisms that could lead to this health outcome or does the epidemiological evidence incorporate biases or other factors that need to be further explored? (author)

EU-CIS joint study project 2. Radiological conditions and risk quantifications in CIS

Energy Technology Data Exchange (ETDEWEB)

Hedemann Jensen, P [Risoe National Lab., Roskilde (Denmark); Likhtariov, I A [Ukrainian Scientific Centre for Radiation Medicine, Kiev (Ukraine); Rolevich, I V [Chernobyl State Committee, Minsk (Belarus); Skryabin, A M [Research Institute of Radiation Medicine, Gomel (Belarus); Demin, V F [Russian Research Centre, Kurchatov Institute, Moscow (Russian Federation); Konstantinov, Y O [Research Institute of Radiation Hygiene, St. Petersburg (Russian Federation)

1995-05-01

The radiological conditions after the Chernobyl accident in the CIS republics Ukraine, Belarus and Russia have been evaluated for the period following 1991. Differential population distributions on dose rate or surface contamination density and differential mass distributions for milk on activity concentration of {sup 137}Cs in milk have been used to calculate individual avertable and residual doses. The residual lifetime doses in the three republics with reference to the year 1991 have been calculated to be of the order of 30 mSv on average. The potential avertable individual lifetime doses are therefore less than the lifetime doses from the natural background radiation in Europe. The corresponding residual individual lifetime risks have been calculated from the European ASQRAD model to be of the order of 0.06-0.14%, depending on age at start of exposure, and assuming an effective half-life of the annual exposure of 10 years and a dose and dose rate effectiveness factor (DDREF) of 2. A risk model is being developed in Russia for the assessment of risks to the exposed populations from atmospheric nuclear weapons tests in the Semipalatinsk region (Altai region) in the forties and fifties. Calculated age-dependent risks from an acute exposure of the Altai population have been compared with results from similar calculations with the ASQRAD model and reasonable agreement has been found between the two models. (au) (11 tabs., 23 ills., 17 refs.).

EU-CIS joint study project 2. Radiological conditions and risk quantifications in CIS

International Nuclear Information System (INIS)

Hedemann Jensen, P.; Likhtariov, I.A.; Rolevich, I.V.; Skryabin, A.M.; Demin, V.F.; Konstantinov, Y.O.

1995-05-01

The radiological conditions after the Chernobyl accident in the CIS republics Ukraine, Belarus and Russia have been evaluated for the period following 1991. Differential population distributions on dose rate or surface contamination density and differential mass distributions for milk on activity concentration of 137 Cs in milk have been used to calculate individual avertable and residual doses. The residual lifetime doses in the three republics with reference to the year 1991 have been calculated to be of the order of 30 mSv on average. The potential avertable individual lifetime doses are therefore less than the lifetime doses from the natural background radiation in Europe. The corresponding residual individual lifetime risks have been calculated from the European ASQRAD model to be of the order of 0.06-0.14%, depending on age at start of exposure, and assuming an effective half-life of the annual exposure of 10 years and a dose and dose rate effectiveness factor (DDREF) of 2. A risk model is being developed in Russia for the assessment of risks to the exposed populations from atmospheric nuclear weapons tests in the Semipalatinsk region (Altai region) in the forties and fifties. Calculated age-dependent risks from an acute exposure of the Altai population have been compared with results from similar calculations with the ASQRAD model and reasonable agreement has been found between the two models. (au) (11 tabs., 23 ills., 17 refs.)

Development of a technical guide for the identification of radiological sources of potential exposure and/or contamination

International Nuclear Information System (INIS)

Reyes, R.; Scott, A.; Falo, G.; Collins, J.; Szrom, F.; Collins, D.

1999-01-01

Radiological assessment of sites with radioactive residues starts with the identification of potential sources. The US Army Center for Health Promotion and Preventive Medicine (USACHPPM) has developed a technical guide that summarizes sources of potential radiological exposures of both civilian and military origin. These sources include those found in the natural environment, in the nuclear fuel cycle, in medical and industrial settings, in the transportation of radioactive materials, in US Army commodities and foreign materiel, and in the use and storage of nuclear weapons. This technical guide is intended to foster awareness of radiological hazards and to provide the reader with the knowledge necessary to take the first step in radiological health risk assessment: recognition of the hazard. Furthermore, this guide can be used in conjunction with other technical guides for performing radiological surveys and field dose assessments in war or peacetime operations. (author)

Critical evaluation of German regulatory specifications for calculating radiological exposure

Energy Technology Data Exchange (ETDEWEB)

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

2015-07-01

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

audit of completion of radiology request form in a nigerian specialist

African Journals Online (AJOL)

X-ray unit of the over a period of six weeks to assess the completeness of filling of the ... outcome. Keywords: audit, radiology, request form, medical education .... times and for making business cases for expansion of services ... such risks.

A consequence index approach to identifying radiological sabotage targets

International Nuclear Information System (INIS)

Altman, W.D.; Hockert, J.W.

1988-01-01

One of the threats to concern to facilities using significant quantities of radioactive material is radiological sabotage. Both the Department of Energy (DOE) and the U.S. Nuclear Regulatory Commission have issued guidance to facilities for radiological sabotage protection. At those facilities where the inventories of radioactive materials change frequently, there is an operational need for a technically defensible method of determining whether or not the inventory of radioactive material at a given facility poses a potential radiological sabotage risk. In order to determine quickly whether a building is a potential radiological sabotage target, Lawrence Livermore National Loaboratory (LLNL) has developed a radiological sabotage consequence index that provides a conservative estimate of the maximum potential off-site consequences of a radiological sabotage attempt involving the facility. This radiological sabotage consequence index can be used by safeguards and security staff to rapidly determine whether a change in building operations poses a potential radiological sabotage risk. In those cases where such a potential risk is identified, a more detailed radiological sabotage vulnerability analysis can be performed

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

Analysis of radioactive contaminations and radiological hazard in Poland after the Chernobyl reactor accident

International Nuclear Information System (INIS)

Zarnowiecki, K.

1988-01-01

It is a report on radiological impact in Poland following the Chernobyl reactor accident prepared in the Central Laboratory for Radiological Protection. The results of measurement and its analysis are presented. Isotopic composition of the contamined air and the concentration of radionuclides are determined. The trajectories of the airborne radioactive material movement from Chernobyl to Poland at the last days of April 1986 are presented. Assessment of the radiological risk of the population is done. 38 refs., 20 figs., 11 tabs. (M.F.W.)

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

Terrorism: the threat of a radiological device

International Nuclear Information System (INIS)

Kingshott, B.F.

2005-01-01

Full text: This paper will discuss terrorism from the perspective of a terrorist organization building and detonating a 'dirty bomb' with a radiological component. The paper will discuss how such devices are made and how security of radiological material world wide will minimize the risk of such devices being used. It will discuss the threat assessments against nuclear waste processing and storage sites, threats to nuclear plants and other sites and the adequacy of current security. It will also discuss the phenomenon of suicide attacks by the bomb carriers and the role of the media in informing and educating the general public of the consequences should such a device be detonated. (author)

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

Value of levels of complexity in the estimation of the risk in interventional radiology procedures; Valor de los indices de complejidad en la estimacion del riesgo en procedimientos de radiologia intervencionista

Energy Technology Data Exchange (ETDEWEB)

Ruiz Cruces, R.; Vano, E.; Hernandez Armas, J.; Carrera Magarino, F.; Rosales, F.; Galan, P.; Solar, M. M.; Perez Martinez, M.; Sanchez Casanueva, R.; Moreno Saiz, C.; Caudepon, F.; Diaz, F.; Gallego Solar, J. J.; Martin-Palanca, A.; Ruiz Munoz-Canela, J. J.; Moreno Rodriguez, F.; Gonzalez de Garay, M.; Canis, M.; Lopez Medina, A.; Moreno Sachez, T.; Pastor Vega, J. M.

2013-07-01

The interventional Radiology (IR) refers to guided procedures with X rays, to develop a diagnostic and/or therapeutic action both in vascular diseases as non-vascular. The progressive increase in the complexity and diversity of interventional procedures make it difficult to objectify the criteria about the dosage provided to patients who are these techniques. Control of radiation doses administered to patients to limit the risks associated with the use of x-rays is not more than one way of improving procedures. For this reason, already completed the ERRAPRI project, we have developed complexity rates to better assess the radiological risk associated with the procedures carried out in a sample of Spanish hospitals. (Author)

Federal Radiological Monitoring and Assessment Center Monitoring Manual Volume 1, Operations

Energy Technology Data Exchange (ETDEWEB)

NSTec Aerial Measurement Systems

2012-07-31

The Monitoring division is primarily responsible for the coordination and direction of: Aerial measurements to delineate the footprint of radioactive contaminants that have been released into the environment. Monitoring of radiation levels in the environment; Sampling to determine the extent of contaminant deposition in soil, water, air and on vegetation; Preliminary field analyses to quantify soil concentrations or depositions; and Environmental and personal dosimetry for FRMAC field personnel, during a Consequence Management Response Team (CMRT) and Federal Radiological Monitoring and Assessment Center (FRMAC) response. Monitoring and sampling techniques used during CM/FRMAC operations are specifically selected for use during radiological emergencies where large numbers of measurements and samples must be acquired, analyzed, and interpreted in the shortest amount of time possible. In addition, techniques and procedures are flexible so that they can be used during a variety of different scenarios; e.g., accidents involving releases from nuclear reactors, contamination by nuclear waste, nuclear weapon accidents, space vehicle reentries, or contamination from a radiological dispersal device. The Monitoring division also provides technicians to support specific Health and Safety Division activities including: The operation of the Hotline; FRMAC facility surveys; Assistance with Health and Safety at Check Points; and Assistance at population assembly areas which require support from the FRMAC. This volume covers deployment activities, initial FRMAC activities, development and implementation of the monitoring and assessment plan, the briefing of field teams, and the transfer of FRMAC to the EPA.

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

Ethical values in radiological protection

International Nuclear Information System (INIS)

Oughton, D.H.

1996-01-01

Issues like consent, equity, control and responsibility are important for an ethical evaluation of radiation risks. This paper discusses the incorporation of ethical values in radiological protection policy and compares how ICRP recommendations promote their use in practice and intervention cases. The paper contends that in cases of intervention, where the overall aim is dose reduction, social and ethical factors are often alluded to when evaluating costs of an action. However, possible ethical or social benefits of intervention measures are seldom raised. On the other hand, when assessing a practice, wherein the net effect is an increase in radiation dose, one is more likely to find an appeal to ethical factors on the benefits side of the equation than with the costs. The paper concludes that all decisions concerning radiological protection should consider both positive and negative ethical aspects. (author)

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

Improving patient follow-up in interventional radiology and radiation-based acts. To reduce the risk of deterministic effects

International Nuclear Information System (INIS)

Etard, Cecile; Aubert, Bernard; Lafont, Marielle; Mougniot, Sandrine; Rousse, Carole; Bey, Eric; Cassagnes, Lucie; Guersen, Joel; Ducou Le Pointe, Hubert; Elhadad, Simon; Georges, Jean-Louis; Nonent, Michel; Paisant-Thouveny, Francine; Salvat, Cecile; Vidal, Vincent; Chauvet, Bruno; Riu, Jean-Luc; Voix, Fabien; Bar, Olivier; Le Du, Dominique; Maccia, Carlo; Lacombe, Pascal; Mertz, Luc; Valery, Charles

2014-04-01

After having presented an example of adverse reaction to interventional radiology (a case of a iatrogenic radiodermatitis), this report first presents the context which creates a risk situation. It describes risks related to the use of ionizing radiations, identifies risk factors and how to make procedures safer, and indicates actions aimed at reducing risks (in a preventive way, in recovery, by attenuation)

Assessment actions and communication of solid cancer development risk in scenarios RDD based on computational simulation

Energy Technology Data Exchange (ETDEWEB)

Bulhosa, Valquiria Miranda; Lima, Zelmo R. de, E-mail: valquiriambrj@gmail.com, E-mail: zelmolima@yahoo.com.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Andrade, Edson Ramos de, E-mail: fisica.dna@gmail.com [Instituto Militar de Engenharia (IME), Rio de Janeiro, RJ (Brazil)

2017-07-01

The complex scenario involving the disposal of radioactive material into the environment can lead to population exposure and serious issues with its unfolding events. In this context, a methodology capable of providing useful basic information, with the least amount of scenario-specific-information, for immediate and future risk assessment is of relevance. For this work a simulation of a Radiological Dispersal Devices involving cesium 137 will be considered, coupling the results of the Health Physics Code System for Evaluating Accidents Involving Radioactive Materials software (HotSpot 3.0.3) and the epidemiological equations of the Radiation Effects Research Foundation (RERF) to support the decision making process. The results of the simulation will be used to help quantify the number of general individuals allocated to areas of higher radiological risk and of interest to medical care by providing the scientific data to develop a more appropriate approach to risk and its communication to the affected population. (author)

Assessment actions and communication of solid cancer development risk in scenarios RDD based on computational simulation

International Nuclear Information System (INIS)

Bulhosa, Valquiria Miranda; Lima, Zelmo R. de; Andrade, Edson Ramos de

2017-01-01

The complex scenario involving the disposal of radioactive material into the environment can lead to population exposure and serious issues with its unfolding events. In this context, a methodology capable of providing useful basic information, with the least amount of scenario-specific-information, for immediate and future risk assessment is of relevance. For this work a simulation of a Radiological Dispersal Devices involving cesium 137 will be considered, coupling the results of the Health Physics Code System for Evaluating Accidents Involving Radioactive Materials software (HotSpot 3.0.3) and the epidemiological equations of the Radiation Effects Research Foundation (RERF) to support the decision making process. The results of the simulation will be used to help quantify the number of general individuals allocated to areas of higher radiological risk and of interest to medical care by providing the scientific data to develop a more appropriate approach to risk and its communication to the affected population. (author)

Radiological risks associated with the various uses of radiation in medicine within the context of their associated benefits

International Nuclear Information System (INIS)

Mettler, F.A.

2001-01-01

Medical procedures represent the largest source of human-made radiation exposure. Most radiation sources expose populations to a risk and these persons may receive no benefit or only an indirect benefit. There are some specific features of medical exposure that make the benefit/risk assessment different from that for other sources of radiation exposure. In medical exposure the exposed person is the direct recipient of an intended benefit that can be compared with the potential risk to that same individual, and the exposure is voluntary. Most radiation exposures should be limited to doses that are as low as reasonably achievable, but in medicine the doses must be at least high enough to obtain an image of diagnostic quality or to eradicate a tumour. The use of very high doses in radiation therapy makes it impossible to make comparisons using effective dose. The paper addresses the radiation risks from diagnostic radiology, nuclear medicine and radiotherapy; discusses the determinants of radiation risk, the measures of benefit and the factors affecting the balance between benefit and risk; and reviews the application of the radiation protection philosophy to medical exposure. (author)

Assessment of the radiological status of the French environment in 2010-2011

International Nuclear Information System (INIS)

Boissieux, Thomas; D'Amico, Donato; Debayle, Christophe; Goyen, Jean-Philippe; Leprieur, Fabrice; Manach, Erwan; Pierrard, Olivier; Tournieux, Damien; Chaptal-Gradoz, Nathalie; Bouisset, Patrick; Boulaud, Denis; Boust, Dominique; Bruno, Valerie; Delabbaye, Pascale; Gallerand, Marie-Odile; Ielsch, Geraldine; Masson, Olivier; Manificat, Guillaume; Peres, Jean-Marc; Renaud, Philippe; Roussel-Debet, Sylvie; Tardieu, Laure; Thebault, Herve; Guldner, Bruno; Wyckaert, Laure

2012-01-01

This report proposes a detailed assessment of the radiological status of the environment in France over the 2010-2011 period. It addresses the radiological monitoring of the environment, presents the national network of measurements of radioactivity in the environment and the main actors of environment monitoring in France, and discusses events and expertise (impact of the Fukushima accident and of some incidents which occurred in France). It presents and comments results of the monitoring of the metropolitan and overseas French territories (atmosphere, soils, sea and coasts, regional assessment), of the monitoring of sites related to nuclear fuel cycle (nuclear sites, old mining sites, industrial sites related to the front-end or back-end of the fuel cycle, waste storage sites), of research centres and nuclear marine bases, of installations using natural or artificial radioactivity sources. It discusses the assessment of the exposure of the French population to ionizing radiation. It indicates information sources dealing with radioactivity monitoring and data publication. A last part proposes a presentation of radioactivity

Dosimetry on the radiological risks prevention in radiotherapy; La dosimetria en la prevencion de riesgos radiologicos en radioterapia

Energy Technology Data Exchange (ETDEWEB)

Fornet R, O. M.; Perez G, F., E-mail: nuclear2@citmahlg.holguin.inf.cu [Delegacion Territorial del CITMA, Peralta 16 esq. P. Feria, Rpto. Peralta, 80400 Holguin (Cuba)

2014-08-15

Dosimetry in its various forms plays a determining role on the radiological risks prevention in radiotherapy. To prove this in this paper is shown an analysis based on the risk matrix method, how the dosimetry can influence in each stages of a radiotherapy service; installation and acceptance, operation, maintenance and calibration. For each one of these stages the role that can play is analyzed as either the initiating event of a radiological accident or limiting barrier of these events of the dosimetric processes used for the individual dosimetry, the area monitoring, fixed or portable, for radiation beam dosimetry and of the patients for a radiotherapy service with cobalt-therapy equipment. The result of the study shows that the application of a prospective approach in the role evaluation of dosimetry in the prevention and mitigation of the consequences of a radiological accident in radiotherapy is crucial and should be subject to permanent evaluation at each development stage of these services. (author)

Guidelines on radiology standards for primary dental care

International Nuclear Information System (INIS)

1994-01-01

A Joint Working Party (JWP) on patient dose reduction in diagnostic radiology was established between the Royal College of Radiologists (RCR) and the National Radiological Protection Board (NRPB) towards the end of 1988. JWP identified a large potential for patient dose reduction on a national scale, and a report of its findings was published in 1990. This guidance was only generally applicable to dental radiology and in 1992 a further joint venture between RCR and NRPB resulted in the formation of a Working Party (WP) to consider all aspects of dental radiology applicable to primary dental care. Dental radiology is one of the largest single groups of radiographic examination performed, although the effective dose per radiograph is small. This means that individual risks from dental radiology are low, but WP has identified a significant potential for reduction in the collective dose and for improvements in the diagnostic quality of radiographs. The WP recommendations cover all aspects of dental radiology: training and examination regimes for dentists and staff, patient selection and clinical justification for radiography, diagnostic interpretation, equipment and procedural aspects, and finally the question of quality assurance in dental radiology. The economic impact of the many recommendations by WP has been considered in some detail. The benefits and cost of each recommendation either have been assigned a monetary value or have been assessed more qualitatively. The conclusion is that there is a strong economic justification for implementation of the full package of recommendations. (Author)

Planning for exercises of the Federal Radiological Monitoring and Assessment Plan

International Nuclear Information System (INIS)

Adler, M.V.

1985-11-01

This report is to be used in planning radiological emergency exercises to test the Federal Radiological Monitoring and Assessment Plan (FRMAP). Although developed for this specific purpose, the document also contains material that may be useful for planning other types of exercises. This report describes the types of exercises that might be used, the steps in planning and conducting the exercises, and the special considerations required for exercises to test the FRMAP. FRMAP exercises typically involve several federal and state agencies. General and specific objectives that could guide these exercises, as well as the possible activities of all the participants - players, controllers, and evaluators - are discussed. The resources that each participating federal agency might provide during an exercise are listed

Initial threat assessment. Radiological risks associated with SevRAO facilities falling within the regulatory supervision responsibilities of FMBA[Russian Federation

Energy Technology Data Exchange (ETDEWEB)

Ilin, Leonid; Kochetkov, Oleg; Simakov, Anatoly; Shandala, Natalya; Savkin, Mikhail; Sneve, Malgorzata K.; Boerretzen, Peer; Jaworska, Alicja; Smith, Graham; Barraclough, Ian; Kruse, Phil

2005-07-01

The purpose of this initial threat assessment is to obtain a view, from the regulatory perspective of FMBA, of the most important issues which require supervision and regulatory development, regarding work which has to be carried out at the Andreeva Bay and Grcmikha. The main radiological threats have been identified and actions to reduce the threats have been proposed. Situations where regulations and procedures for workers on-site need to be developed have been identified. This will be a basis for further development of Russian regulation and procedures. (Author)

Interventional radiology - Health at work references Nr 130

International Nuclear Information System (INIS)

Machacek, C.; Menechal, P.; Megnigbeto, C.; Aubert, B.; Rehel, J.L.; Vidal, J.P.; Biau, A.; Lahaye, T.; Gauron, C.; Barret, C.; Donnarieix, D.; Gambini, D.; Guerin, C.; Marande, J.L.; Marelle, P.; Pierrat, N.

2012-06-01

After having noticed that interventional radiology is used in most of medical and surgical specialities, and indicated the factors influencing operator exposure, this sheet indicates the different types of personnel concerned by these practices, the hazards and risks associated with exposure to direct or scattered radiation, the way risk is assessed and exposure levels are determined (definition of controlled and surveyed areas, personnel classification, selection of a dosimetric control method), how a risk management strategy is defined and implemented (risk reduction methods, technical measures for the installation and for personnel, information and training actions, prevention measures, procedures in case of incident or dysfunction), how medical survey is performed for the personnel, in case of pregnancy, and by using a medical file and performing a post-professional follow-up, and by taking on anomalies and incidents. It also describes how risk management is to be assessed, and mentions some other risks

IAEA Perspectives on Radiological Characterisation

International Nuclear Information System (INIS)

O'Sullivan, Patrick; Ljubenov, Vladan

2012-01-01

quantity and type of radionuclides, their distribution and their physical and chemical states - e.g. see IAEA report no. TRS-389, Radiological Characterization of Shut Down Nuclear Reactors for Decommissioning Purposes. The collection of detailed data on the physical, chemical and radiological conditions in a nuclear facility, including activity calculations, in situ measurements and/or sampling and analysis, facilitates a detailed estimation of risk, cost and waste generation during decommissioning, and supports the selection of the overall dismantling strategy - e.g. partial vs. full decontamination, requirements for shielding and for partial removal of equipment and services - and its detailed planning. It also supports the assessment of different dismantling options and their consequences, including decontamination and dismantling procedures and tools required, and arrangements to ensure the radiological protection of workers, general public and the environment. (authors)

The radiological risk in arc welding; El riesgo radiologico en la soldadura por arco

Energy Technology Data Exchange (ETDEWEB)

Alegria, N.; Campos, M.; Carrion, A.; Herranz, M.; Idoeta, R.; Legarda, F.; Nunez-Lagos, R.; Perez, C.; Rodriguez, S.; Rozas, S.; Sanchez, P.

2011-07-01

We present the current status of a project funded by the Nuclear Safety Council, for the study of the potential radiological risk in arc welding. In the coating of filler material of the electrodes and the soul of the continuous tubular wire welding material are located NORM who present a radioactive activity.

CEC workshop on methods for assessing the offsite radiological consequences of nuclear accidents

International Nuclear Information System (INIS)

Luykx, F.; Sinnaeve, J.

1986-01-01

On Apr 15-19, 1985, in Luxembourg, the Commission of the European Communities (CEC), in collaboration with the Kernforschungszentrum Karlsruhe (KfK), Federal Republic of Germany, and the National Radiological Protection Board (NRPB), United Kingdom, presented a workshop on methods for assessing the offsite radiological consequences of nuclear accidents. The program consisted of eight sessions. The main conclusions, which were presented in the Round Table Session by the individual Session Chairmen, are summarized. Session topics are as follows: Session I: international developments in the field of accident consequence assessment (ACA); Session II: atmospheric dispersion; Session III: food chain models; Session IV: urban contamination; Session V: demographic and land use data; Session VI: dosimetry, health effects, economic and counter measure models; Session VII: uncertainty analysis; and Session VIII: application of probabilistic consequence models as decision aids

Epidemiological methods of assessing risks from low level occupational exposure to ionising radiation

International Nuclear Information System (INIS)

Reissland, J.A.

1982-01-01

The resolution of radiation-attributable malignancies from the background of malignancies which are responsible for about 20% of all deaths in the Western world, presents a formidable challenge to epidemiological methods. Some of the major difficulties facing those with the task of estimating the risks associated with exposure to low level ionising radiation are discussed, particularly in the context of radiological protection. Some of the studies currently in progress are summarised and suggestions are made for other work which may help to contribute to a better understanding of the quantitative aspects of radiation risk assessment. (author)

Factors that elevate the internal radionuclide and chemical retention, dose and health risks to infants and children in a radiological-nuclear emergency

International Nuclear Information System (INIS)

Richardson, R. B.

2009-01-01

The factors that influence the dose and risk to vulnerable population groups from exposure and internal uptake of chemicals are examined and, in particular, the radionuclides released in chemical, biological, radiological, nuclear and explosive events. The paper seeks to identify the areas that would benefit from further research. The intake and body burdens of carbon and calcium were assessed as surrogates for contaminants that either act like or bind to hydrocarbons (e.g. tritium and 14 C) or bone-seeking radionuclides (e.g. 90 Sr and 239 Pu). The shortest turnover times for such materials in the whole body were evaluated for the newborn: 11 d and 0.5 y for carbon and calcium, respectively. However, their biokinetic behaviour is complicated by a particularly high percentage of the gut-absorbed dietary intake of carbon (∼16%) and calcium (∼100%) that is incorporated into the soft tissue and skeleton of the growing neonate. The International Commission on Radiological Protection dose coefficients (Sv Bq -1 ) were examined for 14 radionuclides, including 9 of concern because of their potential use in radiological dispersal devices. The dose coefficients for a 3-month-old are greater than those for adults (2-56 times more for ingestion and 2-12 times for inhalation). The age-dependent dose and exposure assessment of contaminant intakes would improve by accounting for gender and growth where it is currently neglected. Health risk is evaluated as the product of the exposure and hazard factors, the latter being about 10-fold greater in infants than in adults. The exposure factor is also approximately 10-fold higher for ingestion by infants than by adults, and unity for inhalation varying with the contaminant. Qualitative and quantitative physiological and epidemiological evidence supports infants being more vulnerable to cancer and neurological deficit than older children). (authors)

Radiological risk assessment of use of phosphate fertilizers in soil

International Nuclear Information System (INIS)

Kant, K.; Upadhyay, S. B.; Sonkawade, R. G.; Chakarvarti, S. K.

2006-01-01

The radiological impact of the use of phosphate fertilizers in soil is due to the internal irradiation of the lung by the alpha particles, short lived radon-thoron progeny and the external irradiation of the body by gamma rays emitted from radionuclides in situ. This paper describes the results of gamma spectrometric measurements of the concentration of the natural radionuclides namely 226 Ra, 232 Th and 40 K in the soil samples collected from the fields where a variety of phosphate fertilizers are being used by the farmers to enhance the crop yield. Materials and Methods: The experimental work utilizes actual measurements of 226 Ra, 232 Th and 40 K using gamma spectrometry and radon concentration and exhalation rates measurements using solid state nuclear track (LR-115, Type-ll plastic) detectors to asses a first order exposure risk for the persons working in the fields where lot of fertilizers are being used to enhance crop yield in terms of occupational exposure. Results:The concentration of Radium, Thorium and Potassium in the mixed soil sample from crop fields is 16.2 ±0.22, 68.1±1.44 and 875.0±9.68 Bq/kg, where as in barren soil sample is 9.1±0.13, 59.4±1.45 and 668.4± 8.01 Bq/kg respectively. The radium equivalent activity (Ra eq ) in the mixed soil sample from crop fields is 225.9 Bq/kg, where as in barren soil sample is 193.1 Bq/kg. The values of absorbed dose and annual effective dose (indoors and outdoors) are found to vary from 90.87 nGyh -1 to 119.71 nGyh -1 , 0.45 mSv/y to 0.59 mSv/y and 0.11 mSv/y to 0.15 mSv/y respectively in soil sample from crop fields, whereas the value of absorbed dose and annual effective dose (indoors and outdoors) is 92.29 nGyh -1 , 0.45 mSv/y, 0.11 respectively in soil sample collected from barren land. The radon concentration and exhalation rates have also been reported. Conclusion:The activity concentration, exhalation rate and absorbed dose were found to increase substantially with the use of phosphate fertilizers

Mobile technology in radiology resident education.

Science.gov (United States)

Korbage, Aiham C; Bedi, Harprit S

2012-06-01

The authors hypothesized that ownership of a mobile electronic device would result in more time spent learning radiology. Current trends in radiology residents' studying habits, their use of electronic and printed radiology learning resources, and how much of the funds allotted to them are being used toward printed vs electronic education tools were assessed in this study. A survey study was conducted among radiology residents across the United States from June 13 to July 5, 2011. Program directors listed in the Association of Program Directors in Radiology e-mail list server received an e-mail asking for residents to participate in an online survey. The questionnaire consisted of 12 questions and assessed the type of institution, the levels of training of the respondents, and book funds allocated to residents. It also assessed the residents' study habits, access to portable devices, and use of printed and electronic radiology resources. Radiology residents are adopters of new technologies, with 74% owning smart phones and 37% owning tablet devices. Respondents spend nearly an equal amount of time learning radiology from printed textbooks as they do from electronic resources. Eighty-one percent of respondents believe that they would spend more time learning radiology if provided with tablet devices. There is considerable use of online and electronic resources and mobile devices among the current generation of radiology residents. Benefits, such as more study time, may be obtained by radiology programs that incorporate tablet devices into the education of their residents. Copyright © 2012 American College of Radiology. Published by Elsevier Inc. All rights reserved.

Study of radiological risk in breast cancer screening programme at Comunidad Valenciana

International Nuclear Information System (INIS)

Villaescusa, J.I.; Leon, A.; Verdu, G.; Cuevas, M.D.; Salas, M.D.

2001-01-01

It is demonstrated that screening mammography programmes reduce breast cancer mortality considerably. Nevertheless, radiology techniques have an intrinsic risk being the most important late somatic effect the induction of cancer. This study is made in order to evaluate the risk produced into the population by the Cimadon Valenciana Breast Screening Programme. All the calculations are carried out for two risk models, UNSCEAR 94 and NRPB 93. On the one hand, screening series detriment are investigated as a function of doses delivered and other parameters related to population structure and X-ray equipment. And on the other hand, radiation induced cancer probability for a woman who starts at 45 years and remains into the programme until 65 years old is calculated as a function of mammography unit's doses and average compression breast thickness. (author)

Analysis and assessment of the detriment in interventional radiology using biological dosimetry methods

International Nuclear Information System (INIS)

Montoro, A.; Almonacid, M.; Villaescusa, J.I.; Barquinero, J.F.; Rodriguez, P.; Barrios, L.; Verdu, G.; Ramos, M.

2006-01-01

Interventional radiologist and staff members usually are exposed to high levels of scattered radiation. As a result, the exposition to radiation procedures can produce detrimental effects that we would have to know. Effective dose is the quantity that better estimates the radiation risk. For this study we have realized an estimation of the radiological detriment to exposed workers of the Hospital la Fe de Valencia. For it, have been used physical doses registered in detectors T.L.D., and doses estimated by biological dosimetry in lymphocytes of peripheral blood. There has been estimated for every case the probability of effect of skin cancer and of non-solid cancers (leukaemia, lymphoma and myeloma), being compared with the baseline probability of natural effect. Biological doses were obtained by extrapolating the yield of dicentrics and translocations to their respective dose -effect curves. The discrepancies observed between physically recorded doses and biological estimated doses indicate that workers did not always wear their dosimeters or the dosimeters were not always in the radiation field. Cytogenetic studies should be extended to more workers to assess the risk derived from their occupational exposure. (authors)

Analysis and assessment of the detriment in interventional radiology using biological dosimetry methods

Energy Technology Data Exchange (ETDEWEB)

Montoro, A.; Almonacid, M.; Villaescusa, J.I. [Hospital Univ. la Fe de Valen cian, Servicio de Proteccion Radiologica, Valencia (Spain); Barquinero, J.F.; Rodriguez, P. [Universitat Autonom a de Barcelona, Servicio de Dosimetria Biologica, Unidad de Antropologia, Departamento de Biologia Animal, Vegetal y Ecologia., Barcelona (Spain); Barrios, L. [Universidad Autonoma de Barcelona, Dept. de Biologia Celular y Fisiologia. Unidad de Biologia Celular, Barcelona (Spain); Verdu, G.; Ramos, M. [Universidad Politecnica de Valencia, Dept. de Ingenieria Quimica y Nuclear, Valencia, (Spain)

2006-07-01

Interventional radiologist and staff members usually are exposed to high levels of scattered radiation. As a result, the exposition to radiation procedures can produce detrimental effects that we would have to know. Effective dose is the quantity that better estimates the radiation risk. For this study we have realized an estimation of the radiological detriment to exposed workers of the Hospital la Fe de Valencia. For it, have been used physical doses registered in detectors T.L.D., and doses estimated by biological dosimetry in lymphocytes of peripheral blood. There has been estimated for every case the probability of effect of skin cancer and of non-solid cancers (leukaemia, lymphoma and myeloma), being compared with the baseline probability of natural effect. Biological doses were obtained by extrapolating the yield of dicentrics and translocations to their respective dose -effect curves. The discrepancies observed between physically recorded doses and biological estimated doses indicate that workers did not always wear their dosimeters or the dosimeters were not always in the radiation field. Cytogenetic studies should be extended to more workers to assess the risk derived from their occupational exposure. (authors)

The use of Leeds Test Objects in the assessment of the performance of radiological imaging systems: an introduction

International Nuclear Information System (INIS)

Cowen, A.R.

1986-01-01

Over the preceding decade the Leeds Radiological Imaging Group have developed a range of test objects with which to assess the performance of radiological imaging systems. The types of imaging equipment which can be assessed include X-ray image intensifier television systems, small-format 100mm/105mm fluorography systems and radiographic screen-film combinations. We have recently extended our interest to the evaluation of digital radiological imaging equipment including digital subtraction fluorography and digital (greyscale) radiographic imaging systems. These test objects were initially developed for the purpose of evaluating imaging performance under laboratory conditions but they have also proved useful under field (clinical) conditions. (author)

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

Teaching and Assessing Professionalism in Radiology: Resources and Scholarly Opportunities to Contribute to Required Expectations.

Science.gov (United States)

Kelly, Aine Marie; Mullan, Patricia B

2018-05-01

Teaching and assessing trainees' professionalism now represents an explicit expectation for Accreditation Council Graduate Medical Education-accredited radiology programs. Challenges to meeting this expectation include variability in defining the construct of professionalism; limits of traditional teaching and assessment methods, used for competencies historically more prominent in medical education, for professionalism; and emerging expectations for credible and feasible professionalism teaching and assessment practices in the current context of health-care training and practice. This article identifies promising teaching resources and methods that can be used strategically to augment traditional teaching of the cognitive basis for professionalism, including role modeling, case-based scenarios, debriefing, simulations, narrative medicine (storytelling), guided discussions, peer-assisted learning, and reflective practice. This article also summarizes assessment practices intended to promote learning, as well as to inform how and when to assess trainees as their professional identities develop over time, settings, and autonomous practice, particularly in terms of measurable behaviors. This includes assessment tools (including mini observations, critical incident reports, and appreciative inquiry) for authentic assessment in the workplace; engaging multiple sources (self-, peer, other health professionals, and patients) in assessment; and intentional practices for trainees to take responsibility for seeking our actionable feedback and reflection. This article examines the emerging evidence of the feasibility and value added of assessment of medical competency milestones, including professionalism, coordinated by the Accreditation Council Graduate Medical Education in radiology and other medical specialties. Radiology has a strategic opportunity to contribute to scholarship and inform policies in professionalism teaching and assessment practices. Copyright © 2018 The

Relativity Screens for Misvalued Medical Services: Impact on Noninvasive Diagnostic Radiology.

Science.gov (United States)

Rosenkrantz, Andrew B; Silva, Ezequiel; Hawkins, C Matthew

2017-11-01

In 2006, the AMA/Specialty Society Relative Value Scale Update Committee (RUC) introduced ongoing relativity screens to identify potentially misvalued medical services for payment adjustments. We assess the impact of these screens upon the valuation of noninvasive diagnostic radiology services. Data regarding relativity screens and relative value unit (RVU) changes were obtained from the 2016 AMA Relativity Assessment Status Report. All global codes in the 2016 Medicare Physician Fee Schedule with associated work RVUs were classified as noninvasive diagnostic radiology services versus remaining services. The frequency of having ever undergone a screen was compared between the two groups. Screened radiology codes were further evaluated regarding the RVU impact of subsequent revaluation. Of noninvasive diagnostic radiology codes, 46.0% (201 of 437) were screened versus 22.2% (1,460 of 6,575) of remaining codes (P < .001). Most common screens for which radiology codes were identified as potentially misvalued were (1) high expenditures (27.5%) and (2) high utilization (25.6%). The modality and body region most likely to be identified in a screen were CT (82.1%) and breast (90.9%), respectively. Among screened radiology codes, work RVUs, practice expense RVUs, and nonfacility total RVUs decreased in 20.3%, 65.9%, and 75.3%, respectively. All screened CT, MRI, brain, and spine codes exhibited decreased total RVUs. Policymakers' ongoing search for potentially misvalued medical services has disproportionately impacted noninvasive diagnostic radiology services, risking the introduction of unintended or artificial shifts in physician practice. Copyright © 2017 American College of Radiology. Published by Elsevier Inc. All rights reserved.

Age as a factor in assessing risks to patients from the use of x-rays

International Nuclear Information System (INIS)

Le Heron, J.

1996-01-01

Effective dose is currently widely used as a means of quantifying patient dose (and hence patient risk) in diagnostic radiology. Its appeal stems primarily from being able to normalise partial body irradiations into equivalent whole body irradiations, and additionally from being linked to a sound definition of radiation detriment. However there are several aspects of effective dose that should lead to its use being accompnied by a degree of caution. One such factor is age. Calculation of age specific tissue weighting factors for the tissues used in the formulation of effective dose show that the relative contributions of the tissues vary considerably as a function of age. When this is combined with age specific risk factors for cancers and hereditary effects, the implications of a given 'effective dose' for an x-ray procedure depend markedly on the age of the patient. Because of the elderly component of the patient population, the ensuing risks arising from diagnostic radiology are at a level considerably less than that assessed using the population-averaged approach. (author)

An Assessment of the radiological vulnerability for Spanish soils

International Nuclear Information System (INIS)

Trueba, C.; Millan, R.; Schimid, T.; Lago, C.; Gutierrez, J.

2000-01-01

A methodology is presented to assess the radiological vulnerability of soils, based exclusively on their pedagogical properties. The radiological vulnerability defined as the potential capacity of soils to fix or transfer deposited radiocaesium and radiostrontium to plants, is represented in terms of vulnerability indexes. Two pathways are considered, the external irradiation and their transfer through the food chain, where the top horizon and a critical depth of 60 cm is taken into account, respectively, Partial vulnerability indexes are considered for each pathway, which allows a qualitative prediction of the behaviour of the contaminants in soils Global indexes have been obtained as the sum of the partial indexes. The methodology has been applied and validated using a data base consisting of more than 2000 soil profiles selected from all over Spain. This included a pedagogical characterisation and normalisation of the different soil profiles. Results have been obtained for individual soil profiles and with the aid of a GIS, the distribution of the partial and global indexes have been presented for the most representative soil types. (Author)

Probablistic risk assessment methodology application to Indian pressurised heavy water reactors

International Nuclear Information System (INIS)

Babar, A.K.; Grover, R.B.; Mehra, V.K.; Gangwal, D.K.; Chakraborty, G.

1987-01-01

Probabilistic risk assessment in the context of nuclear power plants is associated with models that predict the offsite radiological releases resulting from reactor accidents. Level 1 PRA deals with the identification of accident sequences relevant to the design of a system and also with their quantitative estimation. It is characterised by event tree, fault tree analysis. The initiating events applicable to pressurised heavy water reactors have been considered and the dominating initiating events essential for detailed studies are identified in this paper. Reliability analysis and the associated problems encountered during the case studies are mentioned briefly. It is imperative to validate the failure data used for analysis. Bayesian technique has been employed for the same and a brief account is included herein. A few important observations, e.g. effects of the presence of moderator, made during the application of probabilistic risk assessment methodology are also discussed. (author)

Risk-informed decision making a keystone in advanced safety assessment

International Nuclear Information System (INIS)

Reinhart, M.

2007-01-01

Probabilistic Safety Assessment (PSA) has provided extremely valuable complementary insight, perspective, comprehension, and balance to deterministic nuclear reactor safety assessment. This integrated approach of risk-informed management and decision making has been called Risk-Informed Decision Making (RIDM). RIDM provides enhanced safety, reliability, operational flexibility, reduced radiological exposure, and improved fiscal economy. Applications of RIDM continuously increase. Current applications are in the areas of design, construction, licensing, operations, and security. Operational phase safety applications include the following: technical specifications improvement, risk-monitors and configuration control, maintenance planning, outage planning and management, in-service inspection, inservice testing, graded quality assurance, reactor oversight and inspection, inspection finding significance determination, operational events assessment, and rulemaking. Interestingly there is a significant spectrum of approaches, methods, programs, controls, data bases, and standards. The quest of many is to assimilate the full compliment of PSA and RIDM information and to achieve a balanced international harmony. The goal is to focus the best of the best, so to speak, for the benefit of all. Accordingly, this presentation will address the principles, benefits, and applications of RIDM. It will also address some of the challenges and areas to improve. Finally it will highlight efforts by the IAEA and others to capture the international thinking, experience, successes, challenges, and lessons in RIDM. (authors)

Non-small cell carcinoma: Comparison of postoperative intra- and extrathoracic recurrence assessment capability of qualitatively and/or quantitatively assessed FDG-PET/CT and standard radiological examinations

Energy Technology Data Exchange (ETDEWEB)

Onishi, Yumiko, E-mail: onitan@med.kobe-u.ac.jp [Department of Radiology, Kobe University Graduate School of Medicine, 7-5-2 Kusunoki-cho, Chuo-ku, Kobe 650-0017, Hyogo (Japan); Ohno, Yoshiharu, E-mail: yosirad@kobe-u.ac.jp [Department of Radiology, Kobe University Graduate School of Medicine, 7-5-2 Kusunoki-cho, Chuo-ku, Kobe 650-0017, Hyogo (Japan); Koyama, Hisanobu; Nogami, Munenobu; Takenaka, Daisuke [Department of Radiology, Kobe University Graduate School of Medicine, 7-5-2 Kusunoki-cho, Chuo-ku, Kobe 650-0017, Hyogo (Japan); Matsumoto, Keiko [Department of Radiology, Kobe University Graduate School of Medicine, 7-5-2 Kusunoki-cho, Chuo-ku, Kobe 650-0017, Hyogo (Japan); Department of Radiology, Yamanashi University, Shimokato, Yamanashi (Japan); Yoshikawa, Takeshi; Matsumoto, Sumiaki [Department of Radiology, Kobe University Graduate School of Medicine, 7-5-2 Kusunoki-cho, Chuo-ku, Kobe 650-0017, Hyogo (Japan); Maniwa, Yoshimasa [Division of Thoracic Surgery, Kobe University Graduate School of Medicine, Kobe, Hyogo (Japan); Nishimura, Yoshihiro [Division of Respiratory Medicine, Department of Internal Medicine, Kobe University Graduate School of Medicine, Kobe, Hyogo (Japan); Sugimura, Kazuro [Department of Radiology, Kobe University Graduate School of Medicine, 7-5-2 Kusunoki-cho, Chuo-ku, Kobe 650-0017, Hyogo (Japan)

2011-09-15

Purpose: The purpose of this study was to compare the capability of integrated FDG-PET/CT for assessment of postoperative intra- and extrathoracic recurrence in non-small cell lung cancer (NSCLC) patients with that of standard radiological examinations. Materials and methods: A total of 121 consecutive pathologically diagnosed NSCLC patients (80 males, 41 females; mean age, 71 years) underwent pathologically and surgically confirmed complete resection, followed by prospective integrated FDG-PET/CT and standard radiological examinations. Final diagnosis of recurrence was based on the results of more than 12 months of follow-up and/or pathological examinations. The probability of recurrence was assessed with either method for each patient by using 5-point visual scoring system, and final diagnosis was made by consensus between two readers. ROC analysis was used to compare the capability of the two methods for assessment of postoperative recurrence on a per-patient basis. The ROC-based positive test was used to determine optimal cut-off value for FDG uptake measurement at a site suspected on the basis of qualitatively assessed PET/CT. Finally, sensitivities, specificities and accuracies of all methods were compared by means of McNemar's test. Results: Areas under the curve of qualitatively assessed PET/CT and standard radiological examinations showed no significant differences (p > 0.05). At an optimal cut-off value of 2.5, specificity and accuracy of quantitatively and qualitatively assessed PET/CT were significantly higher than those of qualitatively assessed PET/CT and standard radiological examinations (p < 0.05). Conclusion: Accuracy of assessment of postoperative intra- and extrathoracic recurrence in NSCLC patients by qualitative and/or quantitative FDG-PET/CT is equivalent to or higher than that by standard radiological examinations.

Non-small cell carcinoma: Comparison of postoperative intra- and extrathoracic recurrence assessment capability of qualitatively and/or quantitatively assessed FDG-PET/CT and standard radiological examinations

International Nuclear Information System (INIS)

Onishi, Yumiko; Ohno, Yoshiharu; Koyama, Hisanobu; Nogami, Munenobu; Takenaka, Daisuke; Matsumoto, Keiko; Yoshikawa, Takeshi; Matsumoto, Sumiaki; Maniwa, Yoshimasa; Nishimura, Yoshihiro; Sugimura, Kazuro

2011-01-01

Purpose: The purpose of this study was to compare the capability of integrated FDG-PET/CT for assessment of postoperative intra- and extrathoracic recurrence in non-small cell lung cancer (NSCLC) patients with that of standard radiological examinations. Materials and methods: A total of 121 consecutive pathologically diagnosed NSCLC patients (80 males, 41 females; mean age, 71 years) underwent pathologically and surgically confirmed complete resection, followed by prospective integrated FDG-PET/CT and standard radiological examinations. Final diagnosis of recurrence was based on the results of more than 12 months of follow-up and/or pathological examinations. The probability of recurrence was assessed with either method for each patient by using 5-point visual scoring system, and final diagnosis was made by consensus between two readers. ROC analysis was used to compare the capability of the two methods for assessment of postoperative recurrence on a per-patient basis. The ROC-based positive test was used to determine optimal cut-off value for FDG uptake measurement at a site suspected on the basis of qualitatively assessed PET/CT. Finally, sensitivities, specificities and accuracies of all methods were compared by means of McNemar's test. Results: Areas under the curve of qualitatively assessed PET/CT and standard radiological examinations showed no significant differences (p > 0.05). At an optimal cut-off value of 2.5, specificity and accuracy of quantitatively and qualitatively assessed PET/CT were significantly higher than those of qualitatively assessed PET/CT and standard radiological examinations (p < 0.05). Conclusion: Accuracy of assessment of postoperative intra- and extrathoracic recurrence in NSCLC patients by qualitative and/or quantitative FDG-PET/CT is equivalent to or higher than that by standard radiological examinations.

Radiological diagnostics of muscle diseases

International Nuclear Information System (INIS)

Weber, M.A.; Essig, M.; Kauczor, H.U.

2007-01-01

Muscular diseases are a heterogeneous group of diseases with difficult differential diagnosis. This article reviews morphological and functional radiological techniques for assessment of muscular diseases. Morphological techniques can describe edema-like changes, lipomatous and atrophic changes of muscular tissue. However, these imaging signs are often not disease-specific. As a result, clinicians assign radiology a secondary role in the management of muscular diseases. Meanwhile, functional radiological techniques allow the assessment of muscle fiber architecture, skeletal muscle perfusion, myocellular sodium-homoeostasis, lipid- and energy-phosphate metabolism, etc. By detecting and spatially localizing pathophysiological phenomena, these new techniques can increase the role of radiology in muscular diseases. (orig.)

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

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)

Rational use of diagnostic radiology

International Nuclear Information System (INIS)

Racoveanu, N.T.; Volodin, V.

1992-01-01

Radiologists in USA and UK have since early 1970 questioned the efficacy of various radiological investigations and produced substantial evidence that more rational approaches are necessary. WHO initiated, in 1977, a programme which has issued four technical reports giving practical recommendations on how to rationalise the use of radiological examinations. Three main directions are considered: (1) Abandonment of routine radiological examinations, as procedures with no clinical or epidemiologic significance and which represent a waste of resources and patient dose. (2) Patient selection for various radiological investigations based on clinical criteria (high, intermediate, low yield). Selected patients have an increased prevalence of the given disease and the predictive value of radiological investigation is much higher. (3) Use of diagnostic algorithms with higher cost/efficiency and risk/benefit ratios, improving the outcome of radiological examinations. (author)

Radiology and social media: are private practice radiology groups more social than academic radiology departments?

Science.gov (United States)

Glover, McKinley; Choy, Garry; Boland, Giles W; Saini, Sanjay; Prabhakar, Anand M

2015-05-01

This study assesses the prevalence of use of the most commonly used social media sites among private radiology groups (PRGs) and academic radiology departments (ARDs). The 50 largest PRGs and the 50 ARDs with the highest level of funding from the National Institutes of Health were assessed for presence of a radiology-specific social media account on Facebook, Twitter, Instagram, Pinterest, YouTube, and LinkedIn. Measures of organizational activity and end-user activity were collected, including the number of posts and followers, as appropriate; between-group comparisons were performed. PRGs adopted Facebook 12 months earlier (P = .02) and Twitter 18 months earlier (P = .02) than did ARDs. A total of 76% of PRGs maintained ≥1 account on the social media sites included in the study, compared with 28% of ARDs (P Instagram, 2%. The prevalence of radiology-specific social media accounts for ARDs was: Facebook, 18%; LinkedIn, 0%; Twitter, 24%; YouTube, 6%; Pinterest, 0%; and Instagram, 0%. There was no significant difference between ARDs and PRGs in measures of end-user or organizational activity on Facebook or Twitter. Use of social media in health care is emerging as mainstream, with PRGs being early adopters of Facebook and Twitter in comparison with ARDs. Competitive environments and institutional policies may be strong factors that influence how social media is used by radiologists at the group and department levels. Copyright © 2015 American College of Radiology. Published by Elsevier Inc. All rights reserved.

Long-term follow-up on total reconstruction of the temporomandibular joint - functional, psychosocial and radiological assessments in a case-series study

DEFF Research Database (Denmark)

Andersen, Kristian

Long-term follow-up on total reconstruction of the temporomandibular joint - functional, psychosocial and radiological assessments in a case-series study......Long-term follow-up on total reconstruction of the temporomandibular joint - functional, psychosocial and radiological assessments in a case-series study...

Spent fuel transport in Romania by road: An approach considering safety, risk and radiological consequences

International Nuclear Information System (INIS)

Vieru, G.

2001-01-01

The transport of high-level radioactive wastes, involving Type B packages, is a part of the safety of the Romanian waste management programme and the overall aim of this activity is to promote the safe transport of radioactive materials in Romania. The paper presents a safety case analysis of the transport of a single spent fuel CANDU bundle, using a Romanian built Type B package, from the CANDU type nuclear power plant Cernavoda to the INR Pitesti, in order to be examined within INR's hot-cells facilities. The safety assessment includes the following main aspects: (1) evaluation and analysis of available data on road traffic accidents; (2) estimation of the expected frequency for severe road accident scenarios resulting in potential radionuclide release; and (3) evaluation of the expected radiological consequences and accident risks of transport operations. (author)

The radiological impact of radionuclides dispersed on a regional and global scale: Methods for assessment and their application

International Nuclear Information System (INIS)

1985-01-01

The basic features of models, developed to assess the radiological impact of radionuclides that become dispersed on a regional or global scale, have been reviewed. Particular attention has been given to identifying the important processes that need to be modelled in order to make a reliable estimate of the radiological impact, rather than attempting to judge which models are the most appropriate. Judgements on the latter will be sensitive to the particular application; in some cases a very simple approach may be sufficient, whereas in others a more rigorous analysis may be necessary. Two aspects are important in assessing the radiological impact: these are the exposure of critical groups, and the collective dose in the exposed population

Risk and environmental impact assessment: nuclear and environmental licensing interface

International Nuclear Information System (INIS)