WorldWideScience

Sample records for radiological performance assessments

  1. 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

  2. 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

  3. Improving Site-Specific Radiological Performance Assessments - 13431

    International Nuclear Information System (INIS)

    Tauxe, John; Black, Paul; Catlett, Kate; Lee, Robert; Perona, Ralph; Stockton, Tom; Sully, Mike

    2013-01-01

    An improved approach is presented for conducting complete and defensible radiological site-specific performance assessments (PAs) to support radioactive waste disposal decisions. The basic tenets of PA were initiated some thirty years ago, focusing on geologic disposals and evaluating compliance with regulations. Some of these regulations were inherently probabilistic (i.e., addressing uncertainty in a quantitative fashion), such as the containment requirements of the U.S. Environmental Protection Agency's (EPA's) 40 CFR 191, Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes, Chap. 191.13 [1]. Methods of analysis were developed to meet those requirements, but at their core early PAs used 'conservative' parameter values and modeling approaches. This limited the utility of such PAs to compliance evaluation, and did little to inform decisions about optimizing disposal, closure and long-term monitoring and maintenance, or, in general, maintaining doses 'as low as reasonably achievable' (ALARA). This basic approach to PA development in the United States was employed essentially unchanged through the end of the 20. century, principally by the U.S. Department of Energy (DOE). Performance assessments developed in support of private radioactive waste disposal operations, regulated by the U.S. Nuclear Regulatory Commission (NRC) and its agreement states, were typically not as sophisticated. Discussion of new approaches to PA is timely, since at the time of this writing, the DOE is in the midst of revising its Order 435.1, Radioactive Waste Management [2], and the NRC is revising 10 CFR 61, Licensing Requirements for Land Disposal of Radioactive Waste [3]. Over the previous decade, theoretical developments and improved computational technology have provided the foundation for integrating decision analysis (DA) concepts and objective-focused thinking, plus a Bayesian approach to

  4. Improving Site-Specific Radiological Performance Assessments - 13431

    Energy Technology Data Exchange (ETDEWEB)

    Tauxe, John; Black, Paul; Catlett, Kate; Lee, Robert; Perona, Ralph; Stockton, Tom; Sully, Mike [Neptune and Company, Inc., Los Alamos, New Mexico 87544 (United States)

    2013-07-01

    An improved approach is presented for conducting complete and defensible radiological site-specific performance assessments (PAs) to support radioactive waste disposal decisions. The basic tenets of PA were initiated some thirty years ago, focusing on geologic disposals and evaluating compliance with regulations. Some of these regulations were inherently probabilistic (i.e., addressing uncertainty in a quantitative fashion), such as the containment requirements of the U.S. Environmental Protection Agency's (EPA's) 40 CFR 191, Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes, Chap. 191.13 [1]. Methods of analysis were developed to meet those requirements, but at their core early PAs used 'conservative' parameter values and modeling approaches. This limited the utility of such PAs to compliance evaluation, and did little to inform decisions about optimizing disposal, closure and long-term monitoring and maintenance, or, in general, maintaining doses 'as low as reasonably achievable' (ALARA). This basic approach to PA development in the United States was employed essentially unchanged through the end of the 20. century, principally by the U.S. Department of Energy (DOE). Performance assessments developed in support of private radioactive waste disposal operations, regulated by the U.S. Nuclear Regulatory Commission (NRC) and its agreement states, were typically not as sophisticated. Discussion of new approaches to PA is timely, since at the time of this writing, the DOE is in the midst of revising its Order 435.1, Radioactive Waste Management [2], and the NRC is revising 10 CFR 61, Licensing Requirements for Land Disposal of Radioactive Waste [3]. Over the previous decade, theoretical developments and improved computational technology have provided the foundation for integrating decision analysis (DA) concepts and objective-focused thinking, plus

  5. 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.

  6. 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

  7. Guidelines for radiological performance assessment of DOE low-level radioactive waste disposal sites

    International Nuclear Information System (INIS)

    Case, M.J.; Otis, M.D.

    1988-07-01

    This document provides guidance for conducting radiological performance assessments of Department of Energy (DOE) low-level radioactive waste (LLW) disposal facilities. The guidance is specifically intended to provide the fundamental approach necessary to meet the performance assessment requirements. The document is written for LLW facility operators or other personnel who will manage the performance assessment task. The document is meant to provide guidance for conducting performance assessments in a generally consistent manner at all DOE LLW disposal facilities. The guidance includes a summary of performance objectives to be met by LLW disposal facilities (these objectives are derived from current DOE and other applicable federal regulatory guidelines); specific criteria for an adequate performance assessment and from which a minimum set of required calculations may be determined; recommendations of methods for screening critical components of the analysis system so that these components can be addressed in detail; recommendations for the selection of existing models and the development of site-specific models; recommendations of techniques for comparison of assessment results with performance objectives; and a summary of reporting requirements

  8. Radiological performance assessment for the E-Area Vaults Disposal Facility

    International Nuclear Information System (INIS)

    Cook, J.R.

    2000-01-01

    This report is the first revision to ''Radiological Performance Assessment for the E-Area Vaults Disposal Facility, Revision 0'', which was issued in April 1994 and received conditional DOE approval in September 1994. The title of this report has been changed to conform to the current name of the facility. The revision incorporates improved groundwater modeling methodology, which includes a large data base of site specific geotechnical data, and special Analyses on disposal of cement-based wasteforms and naval wastes, issued after publication of Revision 0

  9. 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)

  10. Radiological performance assessment for the Z-Area Saltstone Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Cook, J.R.; Fowler, J.R. [Westinghouse Savannah River Co., Aiken, SC (United States)

    1992-12-18

    This radiological performance assessment (RPA) for the Savannah River Site (SRS) Saltstone Disposal Facility (SDF) was prepared in accordance with the requirements of Chapter III of the US Department of Energy Order 5820.2A. The Order specifies that an RPA should provide reasonable assurance that a low-level waste (LLW) disposal facility will comply with the performance objectives of the Order. The performance objectives require that: (1) exposures of the general public to radioactivity in the waste or released from the waste will not result in an effective dose equivalent of 25 mrem per year; (2) releases to the atmosphere will meet the requirements of 40 CFR 61; (3) inadvertent intruders will not be committed to an excess of an effective dose equivalent of 100 mrem per year from chronic exposure, or 500 mrem from a single acute exposure; and (4) groundwater resources will be protected in accordance with Federal, State and local requirements.

  11. Radiological performance assessment for the Z-Area Saltstone Disposal Facility

    International Nuclear Information System (INIS)

    Cook, J.R.; Fowler, J.R.

    1992-01-01

    This radiological performance assessment (RPA) for the Savannah River Site (SRS) Saltstone Disposal Facility (SDF) was prepared in accordance with the requirements of Chapter III of the US Department of Energy Order 5820.2A. The Order specifies that an RPA should provide reasonable assurance that a low-level waste (LLW) disposal facility will comply with the performance objectives of the Order. The performance objectives require that: (1) exposures of the general public to radioactivity in the waste or released from the waste will not result in an effective dose equivalent of 25 mrem per year; (2) releases to the atmosphere will meet the requirements of 40 CFR 61; (3) inadvertent intruders will not be committed to an excess of an effective dose equivalent of 100 mrem per year from chronic exposure, or 500 mrem from a single acute exposure; and (4) groundwater resources will be protected in accordance with Federal, State and local requirements

  12. 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

  13. Assessing reader performance in radiology, an imperfect science: Lessons from breast screening

    Energy Technology Data Exchange (ETDEWEB)

    Soh, B.P., E-mail: bsoh6456@uni.sydney.edu.au [Medical Image Optimisation and Perception Group (MIOPeG), Faculty of Health Sciences, University of Sydney, Lidcombe, NSW (Australia); Lee, W.; Kench, P.L.; Reed, W.M.; McEntee, M.F.; Poulos, A.; Brennan, P.C. [Medical Image Optimisation and Perception Group (MIOPeG), Faculty of Health Sciences, University of Sydney, Lidcombe, NSW (Australia)

    2012-07-15

    The purpose of this article is to review the limitations associated with current methods of assessing reader accuracy in mammography screening programmes. Clinical audit is commonly used as a quality-assurance tool to monitor the performance of screen readers; however, a number of the metrics employed, such as recall rate as a surrogate for specificity, do not always accurately measure the intended clinical feature. Alternatively, standardized screening test sets, which benefit from ease of application, immediacy of results, and quicker assessment of quality improvement plans, suffer from experimental confounders, thus questioning the relevance of these laboratory-type screening test sets to clinical performance. Four key factors that impact on the external validity of screening test sets were identified: the nature and extent of scrutiny of one's action, the artificiality of the environment, the over-simplification of responses, and prevalence of abnormality. The impact of these factors on radiological and other contexts is discussed, and although it is important to acknowledge the benefit of standardized screening test sets, issues relating to the relevance of test sets to clinical activities remain. The degree of correlation between performance based on real-life clinical audit and performances at screen read test sets must be better understood and specific causal agents for any lack of correlation identified.

  14. 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

  15. 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)

  16. Radiological performance assessment for the E-Area Vaults Disposal Facility. Appendices A through M

    Energy Technology Data Exchange (ETDEWEB)

    Cook, J.R.

    1994-04-15

    These document contains appendices A-M for the performance assessment. They are A: details of models and assumptions, B: computer codes, C: data tabulation, D: geochemical interactions, E: hydrogeology of the Savannah River Site, F: software QA plans, G: completeness review guide, H: performance assessment peer review panel recommendations, I: suspect soil performance analysis, J: sensitivity/uncertainty analysis, K: vault degradation study, L: description of naval reactor waste disposal, M: porflow input file. (GHH)

  17. Radiological performance assessment for the E-Area Vaults Disposal Facility

    International Nuclear Information System (INIS)

    Cook, J.R.

    1994-01-01

    These document contains appendices A-M for the performance assessment. They are A: details of models and assumptions, B: computer codes, C: data tabulation, D: geochemical interactions, E: hydrogeology of the Savannah River Site, F: software QA plans, G: completeness review guide, H: performance assessment peer review panel recommendations, I: suspect soil performance analysis, J: sensitivity/uncertainty analysis, K: vault degradation study, L: description of naval reactor waste disposal, M: porflow input file

  18. 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...

  19. 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)

  20. 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

  1. Work in support of biosphere assessments for solid radioactive waste disposal. 1. performance assessments, requirements and methodology; criteria for radiological environmental protection

    International Nuclear Information System (INIS)

    Egan, M.J.; Loose, M.; Smith, G.M.; Watkins, B.M.

    2001-10-01

    The first part of this report is intended to assess how the recent Swedish regulatory developments and resulting criteria impose requirements on what should be included in a performance assessment (PA) for the SFR low and medium level waste repository and for a potential deep repository for high level waste. The second part of the report has been prepared by QuantiSci as an input to the development of SSI's PA review methodology. The aim of the third part is to provide research input to the development of radiological protection framework for the environment, for use in Sweden. This is achieved through a review of various approaches used in other fields

  2. 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

  3. 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)

  4. Radiation protection - Performance criteria for laboratories performing cytogenetic triage for assessment of mass casualties in radiological or nuclear emergencies - General principles and application to dicentric assay

    International Nuclear Information System (INIS)

    2008-01-01

    The potential for nuclear and radiological emergencies involving mass casualties from accidental or malicious acts or terrorism requires generic procedures for emergency dose assessment to help the development of medical response capabilities. A mass-casualties incident is defined here as an event that exceeds the local medical resources. Biological dosimetry, based on cytogenetic analysis using the dicentric assay, typically applied for accidental dose assessment, has been defined in ISO 19238. Cytogenetic triage is the use of chromosome damage to evaluate and assess approximately and rapidly radiation doses received by individuals in order to supplement the clinical categorization of casualties. This International Standard focuses on the use of the dicentric assay for rapid cytogenetic triage involving mass-casualty incidents. The primary purpose of this International Standard is to provide a guideline to all laboratories in order to perform the dicentric-bioassay - cytogenetic triage for dose assessment using documented and validated procedures. Secondly, it can facilitate the application of cytogenetic biodosimetry networks to permit comparison of results obtained in different laboratories. Finally, it is expected that laboratories newly commissioned to carry out the cytogenetic triage conform to this International Standard in order to perform the triage reproducibly and accurately. This International Standard is written in the form of procedures to adopt for dicentric-bioassay - cytogenetic triage biological dosimetry for overexposures involving mass radiological casualties. The criteria required for such measurements usually depend on the application of the results: medical management when appropriate, radiation-protection management, record keeping and medical/legal requirements. For example, selected cases can be analysed to produce a more accurate evaluation of high partial-body exposure; secondly, doses can be estimated for persons exposed below the

  5. Radiological performance assessment for the E-Area Vaults Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Cook, J.R.; Hunt, P.D. [Westinghouse Savannah River Co., Aiken, SC (United States)

    1994-04-15

    The E-Area Vaults (EAVs) located on a 200 acre site immediately north of the current LLW burial site at Savannah River Site will provide a new disposal and storage site for solid, low-level, non-hazardous radioactive waste. The EAV Disposal Facility will contain several large concrete vaults divided into cells. Three types of structures will house four designated waste types. The Intermediate Level Non-Tritium Vaults will receive waste radiating greater than 200 mR/h at 5 cm from the outer disposal container. The Intermediate Level Tritium Vaults will receive waste with at least 10 Ci of tritium per package. These two vaults share a similar design, are adjacent, share waste handling equipment, and will be closed as one facility. The second type of structure is the Low Activity Waste Vaults which will receive waste radiating less than 200 mR/h at 5 cm from the outer disposal container and containing less than 10 Ci of tritium per package. The third facility, the Long Lived Waste Storage Building, provides covered, long term storage for waste containing long lived isotopes. Two additional types of disposal are proposed: (1) trench disposal of suspect soil, (2) naval reactor component disposal. To evaluate the long-term performance of the EAVs, site-specific conceptual models were developed to consider: (1) exposure pathways and scenarios of potential importance; (2) potential releases from the facility to the environment; (3) effects of degradation of engineered features; (4) transport in the environment; (5) potential doses received from radionuclides of interest in each vault type.

  6. Radiological performance assessment for the E-Area Vaults Disposal Facility

    International Nuclear Information System (INIS)

    Cook, J.R.; Hunt, P.D.

    1994-01-01

    The E-Area Vaults (EAVs) located on a 200 acre site immediately north of the current LLW burial site at Savannah River Site will provide a new disposal and storage site for solid, low-level, non-hazardous radioactive waste. The EAV Disposal Facility will contain several large concrete vaults divided into cells. Three types of structures will house four designated waste types. The Intermediate Level Non-Tritium Vaults will receive waste radiating greater than 200 mR/h at 5 cm from the outer disposal container. The Intermediate Level Tritium Vaults will receive waste with at least 10 Ci of tritium per package. These two vaults share a similar design, are adjacent, share waste handling equipment, and will be closed as one facility. The second type of structure is the Low Activity Waste Vaults which will receive waste radiating less than 200 mR/h at 5 cm from the outer disposal container and containing less than 10 Ci of tritium per package. The third facility, the Long Lived Waste Storage Building, provides covered, long term storage for waste containing long lived isotopes. Two additional types of disposal are proposed: (1) trench disposal of suspect soil, (2) naval reactor component disposal. To evaluate the long-term performance of the EAVs, site-specific conceptual models were developed to consider: (1) exposure pathways and scenarios of potential importance; (2) potential releases from the facility to the environment; (3) effects of degradation of engineered features; (4) transport in the environment; (5) potential doses received from radionuclides of interest in each vault type

  7. Migration case studies and the implications of humic substances for the radiological performance assessment of radioactive waste repositories

    International Nuclear Information System (INIS)

    Bryan, N.D.; Bernhard, G.; Geipel, G.; Heise, K.H.; Schmeide, K.; Benes, P.

    2005-01-01

    significant. Finally, conclusions are drawn about the likely impact of humic substances upon radiological performance assessment. Although there are still uncertainties and the underlying processes are not understood, all the evidence suggests that humic substances should have an impact, and their effects should at least be considered in performance assessment calculations. (orig.)

  8. Work in support of biosphere assessments for solid radioactive waste disposal. 1. performance assessments, requirements and methodology; criteria for radiological environmental protection

    Energy Technology Data Exchange (ETDEWEB)

    Egan, M.J.; Loose, M.; Smith, G.M.; Watkins, B.M. [QuantiSci Ltd., Henley-on-Thames (United Kingdom)

    2001-10-01

    The first part of this report is intended to assess how the recent Swedish regulatory developments and resulting criteria impose requirements on what should be included in a performance assessment (PA) for the SFR low and medium level waste repository and for a potential deep repository for high level waste. The second part of the report has been prepared by QuantiSci as an input to the development of SSI's PA review methodology. The aim of the third part is to provide research input to the development of radiological protection framework for the environment, for use in Sweden. This is achieved through a review of various approaches used in other fields.

  9. Radiological safety and risk assessment

    International Nuclear Information System (INIS)

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

    1982-02-01

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

  10. Human performance in radiological survey scanning

    International Nuclear Information System (INIS)

    Brown, W.S.; Abelquist, E.W.

    1998-03-01

    The probability of detecting residual contamination in the field using portable radiological survey instruments depends not only on the sensitivity of the instrumentation used in scanning, but also on the surveyor's performance. This report provides a basis for taking human performance into account in determining the minimum level of activity detectable by scanning. A theoretical framework was developed (based on signal detection theory) which allows influences on surveyors to be anticipated and understood, and supports a quantitative assessment of performance. The performance of surveyors under controlled yet realistic field conditions was examined to gain insight into the task and to develop means of quantifying performance. Then, their performance was assessed under laboratory conditions to quantify more precisely their ability to make the required discriminations. The information was used to characterize surveyors' performance in the scanning task and to provide a basis for predicting levels of radioactivity that are likely to be detectable under various conditions by surveyors using portable survey instruments

  11. Human performance in radiological survey scanning

    Energy Technology Data Exchange (ETDEWEB)

    Brown, W.S. [Brookhaven National Lab., Upton, NY (United States); Abelquist, E.W. [Oak Ridge Inst. for Science and Education, TN (United States)

    1998-03-01

    The probability of detecting residual contamination in the field using portable radiological survey instruments depends not only on the sensitivity of the instrumentation used in scanning, but also on the surveyor`s performance. This report provides a basis for taking human performance into account in determining the minimum level of activity detectable by scanning. A theoretical framework was developed (based on signal detection theory) which allows influences on surveyors to be anticipated and understood, and supports a quantitative assessment of performance. The performance of surveyors under controlled yet realistic field conditions was examined to gain insight into the task and to develop means of quantifying performance. Then, their performance was assessed under laboratory conditions to quantify more precisely their ability to make the required discriminations. The information was used to characterize surveyors` performance in the scanning task and to provide a basis for predicting levels of radioactivity that are likely to be detectable under various conditions by surveyors using portable survey instruments.

  12. 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

  13. Test objects for evaluating the performance of radiological imaging systems. Leeds radiological test objects

    International Nuclear Information System (INIS)

    Cowen, A.R.; Clarke, O.F.; Haywood, J.M.; Parker, R.P.

    1985-01-01

    A range of test objects has been developed to assess the imaging performance of conventional and digital radiological imaging systems. These test objects have arisen as a result of involvement in both the laboratory evaluation of radiological imaging systems and the routine maintenance of such equipment in a large diagnostic radiology department. The philosophy behind the design and application of the test objects is briefly described. Particular attention is paid to the advantages of using the threshold-contrast detail-detectability technique to assess overall imaging performance. The great importance of ensuring optimum imaging performance prior to clinical acceptance is stressed. A strategy for implementing the test objects in a clinical department is present. The diagnostic information content of the clinical images which result measures the success of the quality control procedure adopted. (author)

  14. Performance assessment of patient dosimetry services and X-ray quality assurance instruments used in diagnostic radiology

    International Nuclear Information System (INIS)

    Green, S.; Palethrope, J.E.; Peach, D.; Bradley, D.A.

    1999-01-01

    Experiences of the Regional Radiation Physics and Protection Service (RRPPS) in performance assessment of diagnostic X-ray QA instrumentation and on-patient dosemeters are recounted. Issues relating to the provision of realistic and reproducible reference conditions for calibrated X-irradiations are considered and summary statistics from test measurements of dose and kVp meters are provided. For both dose and kVp meters it is indicated that as many as 25% of instruments used in routine use in the U.K. may require some adjustment before they can truly be said to be performing as the manufacturer intended. Results from intercomparison exercises for patient dosimetry services are also discussed. It is apparent that, for those centres participating in the exercise, dose assessments are generally being obtained to within a bias and a relative standard deviation of less then 10%

  15. 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

  16. 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

  17. Diagnostic Accuracy of Focused Assessment with Sonography for Blunt Abdominal Trauma in Pediatric Patients Performed by Emergency Medicine Residents versus Radiology Residents

    Directory of Open Access Journals (Sweden)

    Farhad Heydari

    2018-05-01

    Full Text Available Introduction: Focused assessment with sonography for trauma (FAST has been shown to be useful to detect intraperitoneal free fluid in patients with blunt abdominal trauma (BAT. Objective: We compared the diagnostic accuracy of FAST performed by emergency medicine residents (EMRs and radiology residents (RRs in pediatric patients with BAT. Method: In this prospective study, pediatric patients with BAT and high energy trauma who were referred to the emergency department (ED at Al-Zahra and Kashani hospitals in Isfahan, Iran, were evaluated using FAST, first by EMRs and subsequently by RRs. The reports provided by the two resident groups were compared with the final outcome based on the results of the abdominal computed tomography (CT, operative exploration, and clinical observation. Results: A total of 101 patients with a median age of 6.75 ± 3.2 years were enrolled in the study between January 2013 and May 2014. These patients were evaluated using FAST, first by EMRs and subsequently by RRs. A good diagnostic agreement was noted between the results of the FAST scans performed by EMRs and RRs (κ = 0.865, P < 0.001. The sensitivity, specificity, positive and negative predictive values, and accuracy in evaluating the intraperitoneal free fluid were 72.2%, 85.5%, 52%, 93.3%, and 83.2%, respectively, when FAST was performed by EMRs and 72.2%, 86.7%, 54.2%, 93.5%, and 84.2%, respectively, when FAST was performed by RRs. No significant differences were seen between the EMR- and RR-performed FAST. Conclusion: In this study, FAST performed by EMRs had acceptable diagnostic value, similar to that performed by RRs, in patients with BAT.

  18. 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

  19. 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)

  20. [Optimization of radiological scoliosis assessment].

    Science.gov (United States)

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

    2014-07-01

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

  1. 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)

  2. 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

  3. 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

  4. 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

  5. Development of radiological performance indicators for nuclear power plants

    International Nuclear Information System (INIS)

    Lee, B.S.; Jung, K.H.; Lee, S.H.; Jang, S.Y.

    2000-01-01

    The purpose of this work was to improve the regulatory approach to check the licensee's compliance with regulation regarding radiation protection in operating nuclear power plants (NPPs). The current domestic inspection program for NPPs requires inspectors to conduct compliance-inspection for the systems/equipment and the procedures of NPPs. In this work, we have developed a set of draft radiological performance indicators (PIs) to assess radiation safety in NPPs. The development of PIs was based on the concept that the licensees' implementation of the radiation protection program in NPPs should be able to achieve the goal of radiation protection which the International Commission on Radiological Protection (ICRP) has recommended as ICRP 60 (1991). We selected and/or developed the radiological performance indicators considering the radiation exposure network (source-environment-receptor) for NPPs. The PIs intend to be applied only to normal exposure due to normal operations including transient operational conditions, but not to potential exposure due to accidents. Also, we have chosen the receptor as workers who are occupationally exposed to radiation as well as the members of public who are exposed to radiation from radioactive effluents. The PIs intend to track the past performance rather than to expect the future performance. Finally, the individual PIs do not verify the root cause of the trend of performance; however, they provide the basis for deciding whether the procedures and work management have been properly implemented. Currently a set of 21 draft PIs has been developed for the exposure network in NPPs. For the receptor, the PIs are divided into worker individual dose, worker collective dose and public individual dose. For the environment, the PIs are related to the dose rates of controlled areas, radioactive material concentrations in controlled areas, radioactive contamination in controlled areas and at exit points, and radioactive effluent

  6. Performance assessment

    International Nuclear Information System (INIS)

    Doe, T.

    1985-01-01

    The purpose of performance assessment is to show that the repository is expected to serve its stated function - disposing of radioactive waste safely both during operation and for the postclosure period. Performance assessment is a straightforward concept, but its application may be very complicated. The concept of performance assessment has been clarified by the Nuclear Regulatory Commission (NRC) in their Draft Generic Technical Position on Licensing Assessment Methodology for High-Level Waste Geologic Repositories (NRC, 1984). This document has gone a long way toward defining the criteria that the NRC will use to determine whether or not information from site characterization is adequate to meet the regulations of the Nuclear Regulatory Commission and the Environmental Protection Agency (EPA). A favorable determination is required for issuance of a construction authorization, which is the first major regulatory requirement for developing a working repository. It is, therefore, essential that a research program be developed that not only resolves the outstanding technical issues, but also does it in such a way that the results are clearly applicable to the formal performance assessment and licensing procedures. The definitions of performance assessment are reviewed and the current NRC thinking is summarized

  7. 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...

  8. 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)

  9. Radiology Residents' Performance in Screening Mammography Interpretation

    International Nuclear Information System (INIS)

    Lee, Eun Hye; Lyou, Chae Yeon

    2013-01-01

    To evaluate radiology residents' performance in screening mammography interpretation and to analyze the factors affecting performance. We enrolled 203 residents from 21 institutions and performed mammography interpretation tests. Between the trainee and non-trainee groups, we compared the interpretation score, recall rate, sensitivity, positive predictive value (PPV) and false-positive rate (FPR). We estimated the training effect using the score differences between trainee and non-trainee groups. We analyzed the factors affecting performance between training-effective and non-effective groups. Trainees were superior to non-trainees regarding interpretation score (43.1 vs. 37.1), recall rate (11.0 vs. 15.5%), sensitivity (83.6 vs. 72.0%), PPV (53.0 vs. 32.4%) and FPR (13.5 vs. 25.5). The longer the training period, the better were the interpretation score, recall rate, sensitivity, PPV and FPR (rho = 0.486, -0.375, 0.343, 0.504, -0.446, respectively). The training affected an increase by an average of 6 points; however, 31.6% of institutions showed no effect. A difference was noted in the volume of mammography interpretation during a month (594.0 vs. 476.9) and dedication of breast staff (61.5 vs. 0%) between training-effective and non-effective groups. Trainees showed better performance in mammography interpretation compared to non-trainees. Moreover, performance was correlated with the training period. The factors affecting performance were the volume of mammography interpretation and the dedication of the breast staff.

  10. 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)

  11. 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.

  12. 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

  13. 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

  14. 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)

  15. 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

  16. Radiological risk assessment of a radioactively contaminated site

    International Nuclear Information System (INIS)

    Devgun, J.S.

    1990-01-01

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

  17. Palliative Airway Stenting Performed Under Radiological Guidance and Local Anesthesia

    International Nuclear Information System (INIS)

    Profili, Stefano; Manca, Antonio; Feo, Claudio F.; Padua, Guglielmo; Ortu, Riccardo; Canalis, Giulio C.; Meloni, Giovanni B.

    2007-01-01

    Purpose. To assess the effectiveness of airway stenting performed exclusively under radiological guidance for the palliation of malignant tracheobronchial strictures. Methods. We report our experience in 16 patients with malignant tracheobronchial stricture treated by insertion of 20 Ultraflex self-expandable metal stents performed under fluoroscopic guidance only. Three patients presented dysphagia grade IV due to esophageal malignant infiltration; they therefore underwent combined airway and esophageal stenting. All the procedures were performed under conscious sedation in the radiological room; average procedure time was around 10 min, but the airway impediment never lasted more than 40 sec. Results. We obtained an overall technical success in 16 cases (100%) and clinical success in 14 patients (88%). All prostheses were successfully placed without procedural complications. Rapid clinical improvement with symptom relief and normalization of respiratory function was obtained in 14 cases. Two patients died within 48 hr from causes unrelated to stent placement. Two cases (13%) of migration were observed; they were successfully treated with another stent. Tumor overgrowth developed in other 2 patients (13%); however, no further treatment was possible because of extensive laryngeal infiltration. Conclusions. Tracheobronchial recanalization with self-expandable metal stents is a safe and effective palliative treatment for malignant strictures. Airway stenting performed exclusively under fluoroscopic view was rapid and well tolerated

  18. 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

  19. 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.

  20. Texas' performance assessment work

    International Nuclear Information System (INIS)

    Charbeneau, R.J.; Hertel, N.E.; Pollard, C.G.

    1990-01-01

    The Texas Low-Level Radioactive Waste Disposal Authority is completing two years of detailed on-site suitability studies of a potential low-level radioactive waste disposal site in Hudspeth County, Texas. The data from these studies have been used to estimate site specific parameters needed to do a performance assessment of the site. The radiological impacts of the site have been analyzed as required for a license application. The approach adopted for the performance assessment was to use simplified and yet conservative assumptions with regard to releases, radionuclide transport, and dose calculations. The methodologies employed in the performance assessment are reviewed in the paper. Rather than rely on a single computer code, a modular approach to the performance assessment was selected. The HELP code was used to calculate the infiltration rate through the trench covers and the amount of leachate released from this arid site. Individual pathway analyses used spreadsheet calculations. These calculations were compared with those from other computer models including CRRIS, INGDOS, PATHRAE, and MICROSHIELD copyright, and found to yield conservative estimates of the effective whole body dose. The greatest difficulty in performing the radiological assessment of the site was the selection of reasonable source terms for release into the environment. A surface water pathway is unreasonable for the site. Though also unlikely, the groundwater pathway with exposure through a site boundary well was found to yield the largest calculated dose. The more likely pathway including transport of leachate from the facility through the unsaturated zone and returning to the ground surface yields small doses. All calculated doses associated with normal releases of radioactivity are below the regulatory limits

  1. Radiological assessment of the Esk Estuary

    International Nuclear Information System (INIS)

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

    1993-01-01

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

  2. 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

  3. 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.

  4. 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 ...

  5. 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

  6. Radiology

    International Nuclear Information System (INIS)

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

    1990-01-01

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

  7. 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)

  8. 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

  9. 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)

  10. 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

  11. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-03-01

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

  13. 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

  14. Radiological Assessments and Enhanced Natural Radioactivity

    International Nuclear Information System (INIS)

    Zeevaert, T.; Vanmaercke, H.; Paridaens, K.

    2001-01-01

    The objectives of the research in the field of the environmental impact assessment models performed the Belgian Nuclear Research Centre SCK-CEN are (1) to elaborate and to improve methods and guidelines for the evaluation of restoration options for contaminated sites; (2) to develop, test and improve biosphere models for the performance assessment of radioactive waste disposal in near-surface or geological repositories; (3) to asses the impact of releases from nuclear or industrial installations; (4) to apply new techniques for retrospective radon measurements and to assess radon decay product exposure by combining these techniques; and (5) to increase capabilities in mapping and surveying sites possibly or likely contaminated with enhanced levels of natural radiation. Main achievements in these areas for 2000 are summarised

  15. 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

  16. 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

  17. Radiology

    International Nuclear Information System (INIS)

    Edholm, P.R.

    1990-01-01

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

  18. 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)

  19. 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

  20. 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.

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

    International Nuclear Information System (INIS)

    Lee, Alex; Mathers, Dan

    2003-01-01

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

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

    International Nuclear Information System (INIS)

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

    2007-11-01

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

  3. 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

  4. 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)

  5. 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)

  6. 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.

  7. Quality assessment in radiological imaging methods

    International Nuclear Information System (INIS)

    Herstel, W.

    1985-01-01

    The equipment used in diagnostic radiology is becoming more and more complicated. In the imaging process four components are distinguished, each of which can introduce loss in essential information: the X-ray source, the human body, the imaging system and the observer. In nearly all imaging methods the X-ray quantum fluctuations are a limitation to observation. But there are also technical factors. As an illustration it is shown how in a television scanning process the resolution is restricted by the system parameters. A short review is given of test devices and the results are given of an image comparison based on regular bar patterns. Although this method has the disadvantage of measuring mainly the limiting resolution, the results of the test correlate reasonably well with the subjective appreciations of radiographs of bony structures made by a group of trained radiologists. Fluoroscopic systems should preferably be tested using moving structures under dynamic conditions. (author)

  8. Radioactive Waste Management Complex performance assessment: Draft

    Energy Technology Data Exchange (ETDEWEB)

    Case, M.J.; Maheras, S.J.; McKenzie-Carter, M.A.; Sussman, M.E.; Voilleque, P.

    1990-06-01

    A radiological performance assessment of the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory was conducted to demonstrate compliance with appropriate radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the general public. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the general public via air, ground water, and food chain pathways. Projections of doses were made for both offsite receptors and individuals intruding onto the site after closure. In addition, uncertainty analyses were performed. Results of calculations made using nominal data indicate that the radiological doses will be below appropriate radiological criteria throughout operations and after closure of the facility. Recommendations were made for future performance assessment calculations.

  9. Radioactive Waste Management Complex performance assessment: Draft

    International Nuclear Information System (INIS)

    Case, M.J.; Maheras, S.J.; McKenzie-Carter, M.A.; Sussman, M.E.; Voilleque, P.

    1990-06-01

    A radiological performance assessment of the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory was conducted to demonstrate compliance with appropriate radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the general public. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the general public via air, ground water, and food chain pathways. Projections of doses were made for both offsite receptors and individuals intruding onto the site after closure. In addition, uncertainty analyses were performed. Results of calculations made using nominal data indicate that the radiological doses will be below appropriate radiological criteria throughout operations and after closure of the facility. Recommendations were made for future performance assessment calculations

  10. 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

  11. Performance Assessment National Review Group

    International Nuclear Information System (INIS)

    Lieberman, J.A.; Davis, S.N.; Harleman, D.R.F.

    1985-02-01

    Performance assessment involves predicting the potential radiological impact of a nuclear waste disposal system, taking into account all of the natural and engineered components of the system. It includes the analysis and evaluation of predicted system and component performance to determine compliance with regulatory performance criteria. In the context of the nuclear waste management program, performance assessment has five major purposes: to assist in the evaluation and selection of repository sites; to guide the research, development, and testing programs; to assist in the evaluation of repository designs; to assist in the evaluation of the design and performance of engineered barriers; and to show regulatory compliance and support repository licensing. Current performance assessment methodologies are still in the developmental stage. Only the simplest of bounding calculations have produced quantitative predictions of radionuclide releases. The methodologies require considerable extension and validation before they can provide answers suitable for project decisions and licensing. 135 refs., 9 figs., 1 tab

  12. 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

  13. Study of the performance of diagnostic radiology instruments during calibration

    International Nuclear Information System (INIS)

    Freitas, Rodrigo N. de; Vivolo, Vitor; Potiens, Maria da Penha A.

    2008-01-01

    Full text: The instruments used in diagnostic radiology measurements represent 8 % of the tested instruments by the calibration laboratory of IPEN annually (approximately 1600 in 2007). Considering that the calibration of this kind of instrument is performed biannually it is possible to conclude that almost 300 instruments are being used to measure the air kerma in diagnostic radiology clinics to determine the in beam values (in front of the patient), attenuated measurements (behind the patient) and scattered radiation. This work presents the results of the calibration of the instruments used in mammography, computed tomography, dental and conventional diagnostic radiology dosimetry, performed during the period of 2005 to 2007. Their performances during the calibrations measurements were evaluated. Although at the calibration laboratory there are three available series of radiation quality to this type of calibration (RQR, N and M, according to standards IEC 61267 and ISO 4037-1.), the applications can be assorted (general radiology, computed tomography, mammography, radiation protection and fluoroscopy). Depending on its design and behaviour , one kind of instrument can be used for one or more type of applications. The instruments normally used for diagnostic radiology measurements are ionization chambers with volumes varying from 3 to 1800 cm 3 , and can be cylindrical, spherical or plane parallel plates kind. They usually are sensitive to photon particles, with energies greater than 15 keV and can be used up to 1200 keV. In this work they were tested in X radiation fields from 25 to 150 kV, in specific qualities depending on the utilization of the instrument. The calibration results of 390 instruments received from 2005 to 2007 were analyzed. About 20 instruments were not able to be calibrated due to bad functioning. The calibration coefficients obtained were between 0.88 and 1.24. The uncertainties were always less than ± 3.6% to instruments used in scattered

  14. 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.

  15. 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)

  16. Assessment of radiological risks at the ATLAS experiment

    International Nuclear Information System (INIS)

    Zajacova, Z.

    2009-07-01

    The dissertation addressed three complex radiological issues of the ATLAS experiment at the LHC. Extensive scientific study of the detector activation was performed in order to delineate its radioactive waste zoning. This work involved two independent calculations. One was performed by folding particle fluxes obtained from the GCALOR Monte Carlo radiation transport code with radionuclide production cross sections and the other was done by scoring residual nuclei production with the FLUKA Monte Carlo radiation transport code. In terms of the radioactive waste zoning the results of the two calculations were mutually supportive and in good agreement. To cross-check them on a more detailed level we performed a dedicated study. The cross-check revealed that for most radionuclides the predictions of the two methods are in a very good agreement, within a factor of 2. The production of certain important radionuclides from copper was about 3 times higher by the folding method than with FLUKA. This effect was attributed to the Silberberg- Tsao cross-sections that were used for the folding calculations. Indeed the results were in a better agreement when a different set of cross sections, compiled from predominantly experimental sources, was used. Finally, the largest systematic discrepancies between the two methods were found for the production of 65 Zn in copper 183 Re in tungsten and 56 Co in iron, which was higher with the folding method by more than a factor of 5 for 5 6Co and more than a factor of 20 for the others. These radionuclides are produced almost exclusively by protons through 65 C(p;n) 65 Zn, 56 Fe(p; n) 56 Co and 183 W(p; n) 183 Re reactions. The folding method relied on the Silberberg-Tsao cross sections and consequently treated all hadrons effectively as protons. However, in the end-cap calorimeter protons account for less than 20% of the total hadron flux (not counting neutrons below 20 MeV). Since the contribution of these radionuclides to the total

  17. 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)

  18. 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

  19. 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.

  20. Documentation of in-training assessment for radiology trainees

    International Nuclear Information System (INIS)

    Long, Gillian

    2001-01-01

    AIM: To determine if the assessment of radiology trainees can be improved by modifying the in-training assessment form issued by the Royal College of Radiologists (RCR). MATERIALS AND METHODS: A qualitative study comparing the RCR assessment form with other alternative forms in use in the U.K. Individual semi-structured interviews were conducted with trainees (21) and trainers (18) in Sheffield to collect their views on the RCR form and an alternative form introduced on the North Trent Training Scheme. A postal questionnaire was sent to Heads of Training (24) to find out what assessment forms were in use at other centres and collect their views on the different forms. RESULTS: Trainees and trainers in Sheffield were virtually unanimous in their support of the new North Trent assessment form. The main advantages perceived were the encouragement of appraisal, setting of objectives and feedback from the trainees. Six other radiology training centres were using alternative assessment forms and all believed their forms had advantages over the RCR in-training assessment form. CONCLUSION: The results of this study suggest that the assessment process for radiology trainees can be improved by modifications to the RCR in-training assessment form and allows various recommendations to be made. Long, G. (2001)

  1. 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.

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

    International Nuclear Information System (INIS)

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

    2011-01-01

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

  3. Radiological assessment of an area with uranium residual material

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  4. Exercises for radiological and nuclear emergency response. Planing - performance - evaluation

    International Nuclear Information System (INIS)

    Bayer, A.; Faleschini, J.; Goelling, K.; Stapel, R.; Strobl, C.

    2010-01-01

    The report of the study group emergency response seminar covers the following topics: (A) purpose of exercises and exercise culture: fundamentals and appliances for planning, performance and evaluation; (B) exercises in nuclear facilities; (C) exercises of national authorities and aid organizations on nuclear scenarios; exercises of national authorities and aid organizations on other radiological scenarios; (D) exercises in industrial plants, universities, medical facilities and medical services, and research institutes; (E) transnational exercises, international exercises; (F): exercises on public information.

  5. 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

  6. Radiology

    International Nuclear Information System (INIS)

    Sykora, A.

    2006-01-01

    In this text-book basic knowledge about radiology, biomedical diagnostic methods (radiography, computer tomography), nuclear medicine and safety and radiation protection of personnel on the radiodiagnostic place of work are presented

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

    International Nuclear Information System (INIS)

    1986-06-01

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

  8. 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

  9. Assessment of SRS radiological liquid and airborne contaminants and pathways

    International Nuclear Information System (INIS)

    Jannik, G.T.

    1997-04-01

    This report compiles and documents the radiological critical-contaminant/critical-pathway analysis performed for SRS. The analysis covers radiological releases to the atmosphere and to surface water, which are the principal media that carry contaminants off site. During routine operations at SRS, limited amounts of radionuclides are released to the environment through atmospheric and/or liquid pathways. These releases potentially result in exposure to offsite people. Though the groundwater beneath an estimated 5 to 10 percent of SRS has been contaminated by radionuclides, there is no evidence that groundwater contaminated with these constituents has migrated offsite (Arnett, 1996). Therefore, with the notable exception of radiological source terms originating from shallow surface water migration into site streams, onsite groundwater was not considered as a potential exposure pathway to offsite people

  10. Moss Biomonitoring as a Tool for Radiological Exposure Assessment

    International Nuclear Information System (INIS)

    Barisic, D.; Vekic, B.; Kusan, V.; Spiric, Z.; Frontasyeva, M.

    2013-01-01

    The purpose of this study is to provide an insight into the Atmospheric Deposition of Airborne Radionuclides in Croatia by using the Moss Biomonitoring Technique. Moss samples were collected during the summer of 2010, from 161 locations in Croatia evenly distributed across the entire country. Sampling was performed in accordance with the LRTAP Convention - ICP Vegetation protocol and sampling strategy of the European Programme on Biomonitoring of Heavy Metal Atmospheric Deposition. In addition to the comprehensive qualitative and quantitative chemical analyses of all samples collected determined by NAA, ICP-AES and AAS, 22 out of 161 moss samples were subjected to gamma-spectrometric analyses for assessing activity of the naturally occurring radionuclides. The activities of 40K, 232Th, 137Cs, 226Ra and 238U were determined by using a low background HPGe detector system coupled with an 8192-channel CANBERRA analyzer. The detector system was calibrated using gamma mixed standards supplied by Eckert and Ziegler (Analytics USA). Preliminary research results on the Atmospheric Deposition of Airborne Radionuclides in Croatia by using the Moss Biomonitoring Technique confirm that it may serve as a valuable tool for Radiological Exposure Assessment. This research has the potential for simple, accurate, reliable and affordable environmental radiation control.(author)

  11. Radiological risk assessment for radioactive contamination at landfill site

    International Nuclear Information System (INIS)

    Devgun, J.S.

    1990-01-01

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

  12. 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)

  13. The radiological installation in dental office: selection and performance

    International Nuclear Information System (INIS)

    Cirre, Christian

    2010-01-01

    This thesis for a PhD in dental surgery aimed at identifying and analysing different ways to optimise radiographs. In a first part, the author presents the characteristics of X rays, and dosimetric values used in dental offices. He describes the interaction of X rays with living cells by recalling the discovery of biological effects and the emergence of radiation protection, and by discussing the consequences for the patient as well as for the practician. In the next part, the author comments technological advances of devices, and means available to practicians to improve their performance. He presents X ray tubes, discusses factors which influence ray production, and selection criteria, indicates additional devices (beam application tubes, filtration, collimation), discusses the selection of the receiver (types of receivers used in intra-oral radiology, digital or silver film-based sensors), and describes the picture-taking process (radiological techniques, use of angulators and lead shielding). He finally discusses how to optimise intra-oral dental imagery through good practices which comprise optimisation, selection of apparatuses and devices, performance of the radiological act with a patient sitting in the armchair, and maintenance of a good image quality [fr

  14. Models and parameters for environmental radiological assessments

    International Nuclear Information System (INIS)

    Miller, C.W.

    1984-01-01

    This book presents a unified compilation of models and parameters appropriate for assessing the impact of radioactive discharges to the environment. Models examined include those developed for the prediction of atmospheric and hydrologic transport and deposition, for terrestrial and aquatic food-chain bioaccumulation, and for internal and external dosimetry. Chapters have been entered separately into the data base

  15. Models and parameters for environmental radiological assessments

    Energy Technology Data Exchange (ETDEWEB)

    Miller, C W [ed.

    1984-01-01

    This book presents a unified compilation of models and parameters appropriate for assessing the impact of radioactive discharges to the environment. Models examined include those developed for the prediction of atmospheric and hydrologic transport and deposition, for terrestrial and aquatic food-chain bioaccumulation, and for internal and external dosimetry. Chapters have been entered separately into the data base. (ACR)

  16. 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.

  17. 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

  18. Chernobyl radiological data for accident consequence assessment

    International Nuclear Information System (INIS)

    Bottino, A.; Sacripanti, A.

    1989-01-01

    In this draft is presented the results of a first effort to summarize information related to the radionuclides behaviour in rural areas, in order to estimate pathway parameters to assess accident consequences. This topic encloses relevant aspects concerning contamination of rural environment, the most important being: 1) dry deposition velocities; 2) washout coefficient; 3) accumulation in lakes; 4) migration in soil; 5) winter conditions; 6) filtering effects of forests

  19. 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.

  20. Quality Control Assessment of Radiology Devices in Kerman Province, Iran

    OpenAIRE

    Zahra Jomehzadeh; Ali Jomehzadeh; Mohammad Bagher Tavakoli

    2016-01-01

    Introduction Application of quality control (QC) programs at diagnostic radiology departments is of great significance for optimization of image quality and reduction of patient dose. The main objective of this study was to perform QC tests on stationary radiographic X-ray machines, installed in 14 hospitals of Kerman province, Iran. Materials and Methods In this cross-sectional study, QC tests were performed on 28 conventional radiographic X-ray units in Kerman governmental hospitals, based ...

  1. 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.

  2. 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.

  3. 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

  4. 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

  5. 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

  6. Radiological interpretation 2020: Toward quantitative image assessment

    International Nuclear Information System (INIS)

    Boone, John M.

    2007-01-01

    The interpretation of medical images by radiologists is primarily and fundamentally a subjective activity, but there are a number of clinical applications such as tumor imaging where quantitative imaging (QI) metrics (such as tumor growth rate) would be valuable to the patient’s care. It is predicted that the subjective interpretive environment of the past will, over the next decade, evolve toward the increased use of quantitative metrics for evaluating patient health from images. The increasing sophistication and resolution of modern tomographic scanners promote the development of meaningful quantitative end points, determined from images which are in turn produced using well-controlled imaging protocols. For the QI environment to expand, medical physicists, physicians, other researchers and equipment vendors need to work collaboratively to develop the quantitative protocols for imaging, scanner calibrations, and robust analytical software that will lead to the routine inclusion of quantitative parameters in the diagnosis and therapeutic assessment of human health. Most importantly, quantitative metrics need to be developed which have genuine impact on patient diagnosis and welfare, and only then will QI techniques become integrated into the clinical environment.

  7. Virtual Raters for Reproducible and Objective Assessments in Radiology

    Science.gov (United States)

    Kleesiek, Jens; Petersen, Jens; Döring, Markus; Maier-Hein, Klaus; Köthe, Ullrich; Wick, Wolfgang; Hamprecht, Fred A.; Bendszus, Martin; Biller, Armin

    2016-04-01

    Volumetric measurements in radiologic images are important for monitoring tumor growth and treatment response. To make these more reproducible and objective we introduce the concept of virtual raters (VRs). A virtual rater is obtained by combining knowledge of machine-learning algorithms trained with past annotations of multiple human raters with the instantaneous rating of one human expert. Thus, he is virtually guided by several experts. To evaluate the approach we perform experiments with multi-channel magnetic resonance imaging (MRI) data sets. Next to gross tumor volume (GTV) we also investigate subcategories like edema, contrast-enhancing and non-enhancing tumor. The first data set consists of N = 71 longitudinal follow-up scans of 15 patients suffering from glioblastoma (GB). The second data set comprises N = 30 scans of low- and high-grade gliomas. For comparison we computed Pearson Correlation, Intra-class Correlation Coefficient (ICC) and Dice score. Virtual raters always lead to an improvement w.r.t. inter- and intra-rater agreement. Comparing the 2D Response Assessment in Neuro-Oncology (RANO) measurements to the volumetric measurements of the virtual raters results in one-third of the cases in a deviating rating. Hence, we believe that our approach will have an impact on the evaluation of clinical studies as well as on routine imaging diagnostics.

  8. Radiologic assessment of spinal CSF leakage in spontaneous intracranial hypotension

    International Nuclear Information System (INIS)

    Han, Chang Jin; Kim, Ji Hyung; Kim, Jang Sung; Kim, Sun Yong; Suh, Jung Ho

    1999-01-01

    To assess the usefulness of imaging modalities in the detection of spinal CSF leakage in spontaneous intracranial hypotension. Fifteen patients who complained of postural headache without any preceding cause showed typical brain MR findings of intracranial hypotension, including radiologically confirmed CSF leakage. All fifteen underwent brain MRI and radionuclide cisternography. CT myelography was performed in eight patients and spinal MRI in six. Medical records, imaging findings and the incidence of spinal CSF leakage during each modality were retrospectively reviewed. CSF leakage was most common at the cervicothoracic junction, where in seven of 15 cases it was seen on radionuclide cisternography as increased focal paraspinal activity. Leakage was noted at the mid-tho-racic level in three patients, at the upper thoracic level in two, and at the cervical and lumbar levels in the remaining two. In two patients multiple CSF leaks were noted, and in all, early radioactive accumulation in the bladder was visualized. CT myelography revealed extrathecal and paraspinal contrast leakage in three of eight patients, and among those who underwent spinal MRI, dural enhancement was observed at the site of CSF leakage in all six, abnormal CSF signal in the neural foramen in one, and epidural CSF collection in one. Radionuclide cisternography is a useful method for the detection of CSF leakage in spontaneous intracranial hypotension. CT myelography and spinal MRI help determine the precise location of leakage

  9. 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.

  10. 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

  11. 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

  12. Radiology

    International Nuclear Information System (INIS)

    Meyers, M.A.

    1989-01-01

    This paper reports on disease processes originating within the alimentary tract, may extend through the extraperitoneal spaces, and abnormalities primarily arising within other extraperitoneal sites may significantly affect the bowel. Symptoms and signs may be obscure, delayed, or nonspecific, and the area is generally not accessible to auscultation, palpation, or percussion. Radiologic evaluation thus plays a critical role

  13. 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

  14. Radiological safety assessment of a reference INTOR facility

    International Nuclear Information System (INIS)

    Khan, T.A.; Stasko, R.R.; Watts, R.T.; Shaw, G.; Morrison, C.A.; Russell, S.; Kempe, T.; Zimmerman, R.

    1985-03-01

    This report consists of a number of separate studies all of which were performed in support of INTOR Critical Issue D: Tritium Containment and Personnel Access vs Remote Maintenance. The common thread running through these studies is the radiological safety element in the design and operation of the INTOR facility. The intent is to help establish a firm basis for comparisons between a reactor cell maintenance option which requires personnel access, and one which involves completely remote maintenance

  15. 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.

  16. 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)

  17. 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)

  18. 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)

  19. 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

  20. 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

  1. 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

  2. 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)

  3. 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)

  4. 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

  5. Depleted uranium residual radiological risk assessment for Kosovo sites

    International Nuclear Information System (INIS)

    Durante, Marco; Pugliese, Mariagabriella

    2003-01-01

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

  6. Comparison of radiological and morphologic assessments of myocardial bridges.

    Science.gov (United States)

    Ercakmak, Burcu; Bulut, Elif; Hayran, Mutlu; Kaymaz, Figen; Bilgin, Selma; Hazirolan, Tuncay; Bayramoglu, Alp; Erbil, Mine

    2015-09-01

    In this study we aimed to compare the findings of coronary dual-source computed tomography angiography of myocardial bridges with cadaveric dissections. Forty-one isolated, non-damaged fresh sheep hearts were used in this study. Myocardial bridges of the anterior interventricular branch of the left coronary artery were demonstrated and analyzed by a coronary dual-source computed tomography angiography. Dissections along the left anterior interventricular branch of the left coronary artery were performed by using Zeiss OPMI pico microscope and the length of the bridges were measured. The depths of the myocardial bridges were measured from the stained sections by using the light microscope (Leica DM 6000B). MBs were found in all 41 hearts (100%) during dissections. Dual-source computed tomography angiography successfully detected 87.8% (36 of the 41 hearts) of the myocardial bridges measured on left anterior interventricular branch of left coronary artery. The lengths of the myocardial bridges were found 5-40 and 8-50 mm with dissection and dual-source computed tomography angiography, respectively. And the depths were found 0.7-4.5 mm by dual-source computed tomography angiography and 0.745-4.632 mm morphologically. Comparison of the mean values of the lengths showed statistically significantly higher values (22.0 ± 8.5, 17.7 ± 7.7 mm, p = 0.003) for the dissections. Radiological assessment also effectively discriminated complete bridges from incomplete ones. Our study showed that coronary computed tomography angiography is reliable in evaluating the presence and depth of myocardial bridges.

  7. Enhancement of radiological protection through an internal quality assessment cycle

    International Nuclear Information System (INIS)

    Figueiredo, Filipe Morais de; Gama, Zenewton Andre da Silva

    2012-01-01

    Objective: To determine the level of quality in radiation protection of patients during radiological examination, evaluating the effectiveness of an intervention aimed at enhancing the quality of such a protection. Materials and Methods: A quality improvement cycle was implemented in a radiology service of the Regional Health Administration, in Algarve, Portugal. Based on six quality criteria, an initial evaluation was performed and followed by an intervention focused on the most problematic points (over an eight-month period) and a subsequent quality reassessment. A random sampling (n = 60) has allowed the authors to infer the point estimates and confidence intervals for each criterion, as well as calculating the statistical significance of the results by means of the Z-test. Results: Initially, deficiencies were observed in relation to all the quality criteria. After the intervention, a minimum relative improvement of 33% was observed in five of the six criteria, with statistical significance (p < 0.05) in two of them. The absolute frequency of noncompliance decreased from 38 (first evaluation) to 21 (second evaluation), corresponding to a 44.7% improvement. Conclusion: The first institutional evaluation cycle showed a seemingly incipient improvement margin. However, the implemented intervention was effective in stimulating good practices and improving the level of radiological protection of patients. (author)

  8. 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

  9. Assessment of risk in radiology using malpractice RVU

    International Nuclear Information System (INIS)

    Cristofaro, Massimo; Bellandi, Giuseppe; Squarcione, Salvatore; Petecchia, Antonella; Mammarella, Assunta; Bibbolino, Corrado

    2007-01-01

    Introduction: Analysis on the causes and remedies needed to reduce the incidence of malpractice has been under continual studies, although limited data is available regarding quantitative evaluation of the risk. Objectives: To determine radiological risk in a preventive and quantitative manner and verify if the malpractice relative value units (MP-RVU) are a good indicator of associated risk factors. Materials and methods: Radiological examinations executed by our Radiology Department in 2000-2004 have been codified according to nomenclature HCPCS (Healthcare Common Procedure Coding System) used by United States of America Centers for Medicare and Medicaid Services (CMS). For every examination was calculated the annual weight of malpractice. The data has been groupped in macroaggregates by methodology. The ratio MP-RVU/no. examinations has been considered as an index of insurance risk (MP index) Results: A total of 133,005 examinations were performed, which produced 25,252 MP-RVU points, the total mp index was 0.193. Traditional radiology represents 38% of the examinations, accounting for 8% of MP-RVU with a MP index = 0.039. Ultrasound represents 35% of the examinations, accounting for 23% of MP-RVU with a MP index = 0.125. CT represents 13% of the examinations, accounting for 28% of MP-RVU with a MP index = 0.434. MR represents 11% of the examinations, accounting for 39% of MP-RVU with a MP index = 0.667. Conclusions: Malpractice relative value units (MP-RVU) are indicative of the risk considered globally and when subgrouped. MP index correlates this risk with number of exams carried out divided by methodology. This model providing quantitative data for projects concerning risk management and in allowing the correlation between data obtained in different departments

  10. Assessment of risk in radiology using malpractice RVU

    Energy Technology Data Exchange (ETDEWEB)

    Cristofaro, Massimo [U.O. di Diagnostica per Immagini, Istituto Nazionale per le Malattie Infettive IRCCS, L. Spallanzani Via Portuense, 292, 00149 Rome (Italy)]. E-mail: mcristofar@srm.org; Bellandi, Giuseppe [Servizio di Radiologia ASL 3 Ospedale di Pescia, Via Battisti 2, 51017 Pescia (PT) (Italy)]. E-mail: g.bellandi@mail.vdn.usl3.toscana.it; Squarcione, Salvatore [Direzione Sanitaria Istituto Istituto Nazionale per le Malattie Infettive IRCCS, L. Spallanzani, Via Portuense 292, 00149 Rome (Italy)]. E-mail: squarcione@inmi.it; Petecchia, Antonella [Direzione Sanitaria Istituto Istituto Nazionale per le Malattie Infettive IRCCS, L. Spallanzani, Via Portuense 292, 00149 Rome (Italy)]. E-mail: petecchia@inmi.it; Mammarella, Assunta [Direzione Sanitaria Istituto Istituto Nazionale per le Malattie Infettive IRCCS, L. Spallanzani, Via Portuense 292, 00149 Rome (Italy)]. E-mail: mammarella@inmi.it; Bibbolino, Corrado [U.O. di Diagnostica per Immagini, Istituto Nazionale per le Malattie Infettive IRCCS, L. Spallanzani Via Portuense, 292, 00149 Rome (Italy)]. E-mail: bibbolino@inmi.it

    2007-02-15

    Introduction: Analysis on the causes and remedies needed to reduce the incidence of malpractice has been under continual studies, although limited data is available regarding quantitative evaluation of the risk. Objectives: To determine radiological risk in a preventive and quantitative manner and verify if the malpractice relative value units (MP-RVU) are a good indicator of associated risk factors. Materials and methods: Radiological examinations executed by our Radiology Department in 2000-2004 have been codified according to nomenclature HCPCS (Healthcare Common Procedure Coding System) used by United States of America Centers for Medicare and Medicaid Services (CMS). For every examination was calculated the annual weight of malpractice. The data has been groupped in macroaggregates by methodology. The ratio MP-RVU/no. examinations has been considered as an index of insurance risk (MP index) Results: A total of 133,005 examinations were performed, which produced 25,252 MP-RVU points, the total mp index was 0.193. Traditional radiology represents 38% of the examinations, accounting for 8% of MP-RVU with a MP index = 0.039. Ultrasound represents 35% of the examinations, accounting for 23% of MP-RVU with a MP index = 0.125. CT represents 13% of the examinations, accounting for 28% of MP-RVU with a MP index = 0.434. MR represents 11% of the examinations, accounting for 39% of MP-RVU with a MP index = 0.667. Conclusions: Malpractice relative value units (MP-RVU) are indicative of the risk considered globally and when subgrouped. MP index correlates this risk with number of exams carried out divided by methodology. This model providing quantitative data for projects concerning risk management and in allowing the correlation between data obtained in different departments.

  11. Radiological assessment of radioactive contamination on private clothing

    International Nuclear Information System (INIS)

    Schartmann, F.; Thierfeldt, S.

    2003-01-01

    In the very rare, cases where private clothing of persons working in a nuclear installation are inadvertently contaminated and this contamination is not detected when leaving the facility, there may be radiological consequences for this person as well as for members of his or her family. The VGB (Technische Vereinigung der Grosskraftwerksbetreiber) in Germany has investigated in detail the spread of contamination in nuclear power plants. Part of this evaluation programme was a radiological analysis which has been carried out by Brenk Systemplanung GmbH (Aachen/Germany). The radiological analysis started with the definition of the source term. It is highly unlikely that activities of more than 5 kBq 60 Co could leave a plant undetected on the body or the clothes. Nevertheless activities up to 50 kBq and different nuclide vectors were regarded. It has been found that 60 Co is the most important contaminant. The radiological analysis focusses on two types of contamination: particles and surface contamination. The pathways by which such a contamination can lead to an exposure by external irradiation or by ingestion depend on the type of contamination and are analysed in detail. For example, a particle could be retained in pockets or other parts of clothing and may lead to prolonged external irradiation until the piece of clothing is washed. The analysis is performed on the basis of conservative to realistic assumptions. In conclusion, the analysis has shown that especially particle contamination needs to be focussed on. However, by the advanced detection equipment in German plants doses which may pose a health hazard can safely be excluded. (authors)

  12. 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.

  13. 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

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

    International Nuclear Information System (INIS)

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

    1989-01-01

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

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

    International Nuclear Information System (INIS)

    Campos, M.P. de.

    1994-01-01

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

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

    International Nuclear Information System (INIS)

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

    1984-10-01

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

  17. Radiology

    International Nuclear Information System (INIS)

    Lissner, J.

    1985-01-01

    Diagnostic radiology is still the foremost of all innovative medical disciplines. This has many advantages but also some handicaps, e.g. the siting problem of medical equipment whose clinical potential is not fully known. This applies in particular to nuclear spin tomography, where the Laender governments and the Scientific Council seen to agree that all universities should have the appropriate equipment as soon as possible in order to intensify interdisciplinary research. Formerly, in the case of computerized tomography, there was less readiness. As a result, the siting of CT equipment is less organically structured. A special handicap of innovative fields is the problem of training and advanced training. The Chamber of Medicine and the Association of Doctors Participating in the Health Insurance Plan have issued regulations aimed at a better standardisation in this field. (orig.) [de

  18. 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

  19. 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.

  20. Analysis of data related to the updating of diagnosis reference levels in radiology and nuclear medicine. Assessment 2007-2008

    International Nuclear Information System (INIS)

    2010-01-01

    This report presents the results of the analysis of 'patient' dosimetric data which radiology and nuclear medicine establishments must supply every year to the IRSN (the French Radioprotection and Nuclear Safety Institute) according to a decree related to diagnosis reference levels in radiology and nuclear medicine. The analysed dosimetric data concern assessments performed during 2007 and 2008. For the different concerned practices (radiology, scanography, nuclear medicine), the report proposes a presentation and a discussion of global data, and then a presentation of data either for different types of examination on adults and on children, or for the different parts of the body

  1. 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.

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

    Science.gov (United States)

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

    2017-01-01

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

  3. 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

  4. Principles and issues in radiological ecological risk assessment.

    Science.gov (United States)

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

    2003-01-01

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

  5. 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

  6. Efficient radiological assessment of the internal snapping hip syndrome

    International Nuclear Information System (INIS)

    Wunderbaldinger, P.; Bremer, C.; Matuszewski, L.; Marten, K.; Turetschek, K.; Rand, T.

    2001-01-01

    The aim of this study was to evaluate the diagnostic value/significance of various imaging techniques for demonstrating the underlying causative pathology of clinically suspected internal snapping hip syndrome. We intended to define the most efficient diagnostic imaging algorithm that leads to a specific definite therapy for this rare hip disorder. The imaging studies of 54 patients (43 women, 11 men, average age 58 years) with the clinical suspicion of internal snapping hip syndrome were compared for their diagnostic value/significance for finding the underlying pathology. Radiological workup included plain radiographs of the pelvis and hip joints (n=54), ultrasound (US) of the hip joints (n=29), computed tomography (CT) of the pelvis and proximal femur (n=17), and magnetic resonance imaging (MRI) of the pelvis/hip joint (n=21). In order to establish an efficient diagnostic algorithm we compared the diagnostic value of each imaging technique alone and in combination with the other methods. The underlying causative pathology could be established in 37% of patients (n=20) by the use of conventional radiographs alone and in 46% of the patients (n=25) by US alone, and in combination in 83% of the patients (n=45). By adding CT to the radiological workup, we established final diagnosis in 88% (in combination with X-ray; n=15/17) and 94% (together with X-ray and US; n=16/17) of the patients. Whenever MR imaging was used a causative pathology was found in all patients (100%; n=21). The most efficient radiological algorithm in the assessment of patients with internal snapping hip syndrome is the combination of plain radiography and US. MR imaging can be retained for unresolved and difficult cases. (orig.)

  7. Process of performance assessment

    International Nuclear Information System (INIS)

    King, C.M.; Halford, D.K.

    1987-01-01

    Performance assessment is the process used to evaluate the environmental consequences of disposal of radioactive waste in the biosphere. An introductory review of the subject is presented. Emphasis is placed on the process of performance assessment from the standpoint of defining the process. Performance assessment, from evolving experience at DOE sites, has short-term and long-term subprograms, the components of which are discussed. The role of mathematical modeling in performance assessment is addressed including the pros and cons of current approaches. Finally, the system/site/technology issues as the focal point of this symposium are reviewed

  8. 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

  9. A Performance Weighted Collaborative Filtering algorithm for personalized radiology education.

    Science.gov (United States)

    Lin, Hongli; Yang, Xuedong; Wang, Weisheng; Luo, Jiawei

    2014-10-01

    Devising an accurate prediction algorithm that can predict the difficulty level of cases for individuals and then selects suitable cases for them is essential to the development of a personalized training system. In this paper, we propose a novel approach, called Performance Weighted Collaborative Filtering (PWCF), to predict the difficulty level of each case for individuals. The main idea of PWCF is to assign an optimal weight to each rating used for predicting the difficulty level of a target case for a trainee, rather than using an equal weight for all ratings as in traditional collaborative filtering methods. The assigned weight is a function of the performance level of the trainee at which the rating was made. The PWCF method and the traditional method are compared using two datasets. The experimental data are then evaluated by means of the MAE metric. Our experimental results show that PWCF outperforms the traditional methods by 8.12% and 17.05%, respectively, over the two datasets, in terms of prediction precision. This suggests that PWCF is a viable method for the development of personalized training systems in radiology education. Copyright © 2014. Published by Elsevier Inc.

  10. 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)

  11. The radiological impact associated with the recycling of actinides and fission products. A global assessment

    International Nuclear Information System (INIS)

    Dodd, D.H.

    1996-05-01

    This report describes the results of a literature study performed to identify any significant differences in the public radiological impact associated with existing nuclear fuel cycles and partitioning and transmutation (P and T) based fuel cycles. The study was performed in the framework of ECN Nuclear Energy's RAS (Recyclage van Actiniden en Splijtingsprodukten) research programme. Two reference 'once through' cycles and five 'advanced' fuel cycles were analysed. The five 'advanced' fuel cycles all incorporate technologies for the partitioning and transmutation of the long-lived radionuclides present in high level radioactive waste. Currently, only a limited amount of information on these 'advanced' fuel cycles is available. The assessment of the radiological impact associated with these cycles is therefore by necessity of a general nature. (orig./WL)

  12. 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)

  13. 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.

  14. Benign breast diseases. Radiology, pathology, risk assessment. 2. ed.

    International Nuclear Information System (INIS)

    Chinyama, Catherine N.

    2014-01-01

    Radiological and pathological correlation of the full range of benign breast lesions, with emphasis on screen-detected lesions. Detailed discussion of risk assessment. Revised and updated edition, with a new chapter on gynaecomastia. Ideal aid to the management of patients with benign or indeterminate breast lesions in a multidisciplinary setting. The second edition of this book has been extensively revised and updated. There have been numerous scientific advances in the radiology, pathology and risk assessment of benign breast lesions since the publication of the first edition. The first edition concentrated on screen-detected lesions, which has since been rectified; new symptomatic and screen-detected lesions are discussed in the second edition and include: mastitis and breast abscesses, idiopathic granulomatous mastitis, diabetic mastopathy, phyllodes tumours, gynaecomastia and pseudoangiomatous stromal hyperplasia. The chapters on columnar cell lesions and mucocele-like lesions have been extensively updated. Where applicable, genetic analysis of the benign lesions, which is becoming part of personalised medicine in the field of breast cancer, has been included. The book also presents detailed analyses of the main models, such as the Gail Model, used to assess the subsequent risk of breast cancer in individuals. The current trend in the management of all cancers is preventative. Screening mammography detects early curable cancers as well as indeterminate lesions, the latter of which are invariably pathologically benign. The author has collated important benign lesions and, based on peer-reviewed publications, has documented the relative risk of subsequent cancer to allow the patient and the clinician to implement preventative measures where possible. This book will therefore serve as an essential component of multidisciplinary management of patients with symptomatic and screen-detected benign breast lesions.

  15. 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

  16. Benign breast diseases. Radiology, pathology, risk assessment. 2. ed.

    Energy Technology Data Exchange (ETDEWEB)

    Chinyama, Catherine N. [Princess Elizabeth Hospital, Le Vauquiedor, St. Martin' s Guernsey, Channel Islands (United Kingdom); Brighton and Sussex Medical School, Brighton (United Kingdom)

    2014-04-01

    Radiological and pathological correlation of the full range of benign breast lesions, with emphasis on screen-detected lesions. Detailed discussion of risk assessment. Revised and updated edition, with a new chapter on gynaecomastia. Ideal aid to the management of patients with benign or indeterminate breast lesions in a multidisciplinary setting. The second edition of this book has been extensively revised and updated. There have been numerous scientific advances in the radiology, pathology and risk assessment of benign breast lesions since the publication of the first edition. The first edition concentrated on screen-detected lesions, which has since been rectified; new symptomatic and screen-detected lesions are discussed in the second edition and include: mastitis and breast abscesses, idiopathic granulomatous mastitis, diabetic mastopathy, phyllodes tumours, gynaecomastia and pseudoangiomatous stromal hyperplasia. The chapters on columnar cell lesions and mucocele-like lesions have been extensively updated. Where applicable, genetic analysis of the benign lesions, which is becoming part of personalised medicine in the field of breast cancer, has been included. The book also presents detailed analyses of the main models, such as the Gail Model, used to assess the subsequent risk of breast cancer in individuals. The current trend in the management of all cancers is preventative. Screening mammography detects early curable cancers as well as indeterminate lesions, the latter of which are invariably pathologically benign. The author has collated important benign lesions and, based on peer-reviewed publications, has documented the relative risk of subsequent cancer to allow the patient and the clinician to implement preventative measures where possible. This book will therefore serve as an essential component of multidisciplinary management of patients with symptomatic and screen-detected benign breast lesions.

  17. 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

  18. Assessment of the radiation risk from diagnostic radiology

    International Nuclear Information System (INIS)

    Streffer, C.; Mueller, W.U.

    1995-01-01

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

  19. NRC performance assessment program

    International Nuclear Information System (INIS)

    Coplan, S.M.

    1986-01-01

    The U.S. Nuclear Regulatory Commission's (NRC) performance assessment program includes the development of guidance to the U.S. Department of Energy (DOE) on preparation of a license application and on conducting the studies to support a license application. The nature of the licensing requirements of 10 CFR Part 60 create a need for performance assessments by the DOE. The NRC and DOE staffs each have specific roles in assuring the adequacy of those assessments. Performance allocation is an approach for determining what testing and analysis will be needed during site characterization to assure that an adequate data base is available to support the necessary performance assessments. From the standpoint of establishing is implementable methodology, the most challenging performance assessment needed for licensing is the one that will be used to determine compliance with the U.S. Environmental Protection Agency's (EPA) containment requirement

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

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  1. 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

  2. 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

  3. "Flipping" the introductory clerkship in radiology: impact on medical student performance and perceptions.

    Science.gov (United States)

    Belfi, Lily M; Bartolotta, Roger J; Giambrone, Ashley E; Davi, Caryn; Min, Robert J

    2015-06-01

    Among methods of "blended learning" (ie, combining online modules with in-class instruction), the "flipped classroom" involves student preclass review of material while reserving class time for interactive knowledge application. We integrated blended learning methodology in a "flipped" introductory clerkship in radiology, and assessed the impact of this approach on the student educational experience (performance and perception). In preparation for the "flipped clerkship," radiology faculty and residents created e-learning modules that were uploaded to an open-source website. The clerkship's 101 rising third-year medical students were exposed to different teaching methods during the course, such as blended learning, traditional lecture learning, and independent learning. Students completed precourse and postcourse knowledge assessments and surveys. Student knowledge improved overall as a result of taking the course. Blended learning achieved greater pretest to post-test improvement of high statistical significance (P value, .0060) compared to lecture learning alone. Blended learning also achieved greater pretest to post-test improvement of borderline statistical significance (P value, .0855) in comparison to independent learning alone. The difference in effectiveness of independent learning versus lecture learning was not statistically significant (P value, .2730). Student perceptions of the online modules used in blended learning portions of the course were very positive. They specifically enjoyed the self-paced interactivity and the ability to return to the modules in the future. Blended learning can be successfully applied to the introductory clerkship in radiology. This teaching method offers educators an innovative and efficient approach to medical student education in radiology. Copyright © 2015 AUR. Published by Elsevier Inc. All rights reserved.

  4. 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)

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

    International Nuclear Information System (INIS)

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

    1993-01-01

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

  6. 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)

  7. Radiological Instrumentation Assessment for King County Wastewater Treatment Division

    International Nuclear Information System (INIS)

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

    2005-01-01

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

  8. Focused process improvement events: sustainability of impact on process and performance in an academic radiology department.

    Science.gov (United States)

    Rosenkrantz, Andrew B; Lawson, Kirk; Ally, Rosina; Chen, David; Donno, Frank; Rittberg, Steven; Rodriguez, Joan; Recht, Michael P

    2015-01-01

    To evaluate sustainability of impact of rapid, focused process improvement (PI) events on process and performance within an academic radiology department. Our department conducted PI during 2011 and 2012 in CT, MRI, ultrasound, breast imaging, and research billing. PI entailed participation by all stakeholders, facilitation by the department chair, collection of baseline data, meetings during several weeks, definition of performance metrics, creation of an improvement plan, and prompt implementation. We explore common themes among PI events regarding initial impact and durability of changes. We also assess performance in each area pre-PI, immediately post-PI, and at the time of the current study. All PI events achieved an immediate improvement in performance metrics, often entailing both examination volumes and on-time performance. IT-based solutions, process standardization, and redefinition of staff responsibilities were often central in these changes, and participants consistently expressed improved internal leadership and problem-solving ability. Major environmental changes commonly occurred after PI, including a natural disaster with equipment loss, a change in location or services offered, and new enterprise-wide electronic medical record system incorporating new billing and radiology informatics systems, requiring flexibility in the PI implementation plan. Only one PI team conducted regular post-PI follow-up meetings. Sustained improvement was frequently, but not universally, observed: in the long-term following initial PI, measures of examination volume showed continued progressive improvements, whereas measures of operational efficiency remained stable or occasionally declined. Focused PI is generally effective in achieving performance improvement, although a changing environment influences the sustainability of impact. Thus, continued process evaluation and ongoing workflow modifications are warranted. Copyright © 2015 American College of Radiology

  9. 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

  10. 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

  11. 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

  12. 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

  13. Radiological impact assessment in Bagjata uranium deposit: a case study

    International Nuclear Information System (INIS)

    Sarangi, A.K.; Bhowmik, S.C.; Jha, V.N.

    2007-01-01

    The uranium ore mining facility, in addition to the desirable product, produces wastes in the form of environmental releases or effluents to air, water and soil. The toxicological and other (non-radiological) effects are generally addressed in EIA/EMP studies as per MOEF guidelines. Since the uranium ore is radioactive, it is desirable to conduct a study on radiological effects considering the impacts of radiological releases to the environment. Before undertaking the commercial mining operations at Bagjata uranium deposit in the Singhbhum east district of Jharkhand, pre-operational radiological base line data were generated and a separate study on radiological impact on various environmental matrices was conducted in line with the International Atomic Energy Agency's laid out guidelines. The paper describes the philosophy of such studies and the findings that helped in formulating a separate environmental management plan. (author)

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

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  15. 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.)

  16. 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.)

  17. 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)

  18. 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)

  19. Quality Control Assessment of Radiology Devices in Kerman Province, Iran

    Directory of Open Access Journals (Sweden)

    Zahra Jomehzadeh

    2016-03-01

    Full Text Available Introduction Application of quality control (QC programs at diagnostic radiology departments is of great significance for optimization of image quality and reduction of patient dose. The main objective of this study was to perform QC tests on stationary radiographic X-ray machines, installed in 14 hospitals of Kerman province, Iran. Materials and Methods In this cross-sectional study, QC tests were performed on 28 conventional radiographic X-ray units in Kerman governmental hospitals, based on the protocols and criteria recommended by the Atomic Energy Organization of Iran (AEOI, using a calibrated Gammex QC kit. Each section of the QC kit incorporated different models. Results Based on the findings, kVp accuracy, kVp reproducibility, timer accuracy, timer reproducibility, exposure reproducibility, mA/timer linearity, and half-value layer were not within the acceptable limits in 25%, 4%, 29%, 18%, 11%, 12%, and 7% of the evaluated units (n=28, respectively. Conclusion As radiographic X-ray equipments in Kerman province are relatively old with a high workload, it is recommended that AEOI modify the current policies by changing the frequency of QC test implementation to at least once a year.

  20. Honorary authorship in radiologic research articles: assessment of frequency and associated factors.

    Science.gov (United States)

    Eisenberg, Ronald L; Ngo, Long; Boiselle, Philip M; Bankier, Alexander A

    2011-05-01

    To quantify the frequency of perceived honorary authorship in radiologic journals and to identify specific factors that increase its prevalence. This study qualified for exempt status by the institutional review board. An electronic survey was sent to first authors of all original research articles published in Radiology and European Radiology over 3 years. Questions included guidelines used for determining authorship, contributions of coauthors, the perception of honorary authorship, and demographic information. Univariable analysis of sample proportions was performed by using χ(2) tests. Multivariable logistic regression models were used to assess the independent factors that were associated with the probability of perceiving honorary authorship. Of the 392 (29.3%) of 1338 first authors who responded to the survey, 102 (26.0%) perceived that one or more coauthors did not make sufficient contributions to merit being included as an author. Of the 392 respondents, 231 (58.9%) stated that one or more coauthors performed only "nonauthor" tasks according to International Committee of Medical Journal Editors criteria. Factors associated with an increased first-author perception of honorary authorship included lower academic rank (adjusted odds ratio [OR]: 2.89; 95% confidence interval [CI]: 1.66, 5.06), as well as working in an environment in which the section or department head was automatically listed as an author (adjusted OR: 3.80; 95% CI: 2.13, 6.79). The percentage of honorary authorship was significantly higher (P = .019) among respondents who did not follow journal requirements for authorship. The rate of perceived honorary authorship (overall, 26.0%) was substantially more frequent among respondents of lower academic rank and in those working in an environment in which their section or department head was automatically listed as an author. http://radiology.rsna.org/lookup/suppl/doi:10.1148/radiol.11101500/-/DC1. RSNA, 2011

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

    International Nuclear Information System (INIS)

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

    2007-01-01

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

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

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  3. Radiological 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

  4. 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)

  5. Radiology residents' comprehension of the breast imaging reporting and data system: The ultrasound lexicon and final assessment category

    International Nuclear Information System (INIS)

    Jeong, Sun Hye; Lee, Eun Hye; Roh, Yun Ho; Kim, Min Jung; Youk, Ji Hyun; Yoon, Jung Hyun; Kim, Sung Hun; Kim, You Me

    2017-01-01

    To evaluate radiology residents' performance in interpretation and comprehension of breast ultrasonographic descriptors in the Breast Imaging Reporting and Data System (BI-RADS) to suggest the adequate duration of training in breast ultrasonography. A total of 102 radiology residents working in the Department of Radiology were included in this study. They were asked to answer 16 questions about the ultrasonographic lexicon and 11 questions about the BI-RADS category. We analyzed the proportion of correct answers according to the radiology residents’ year of training and duration of breast imaging training. With respect to the duration of breast imaging training, the proportion of correct answers for lexicon descriptors ranged from 77.2% to 81.3% (p = 0.368) and the proportion of correct answers for the BI-RADS category was highest after three-four months of training compared with after one month of training (p = 0.033). The proportion of correct answers for lexicon descriptors and BI-RADS category did not differ significantly according to the year of residency training. Radiology residents' comprehension of the BI-RADS category on breast ultrasonography was not associated with their year of residency training. Based on our findings, radiology residents' assessment of the BI-RADS category was significantly improved with three-four months of training compared with one month of training

  6. Radiology residents' comprehension of the breast imaging reporting and data system: The ultrasound lexicon and final assessment category

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Sun Hye; Lee, Eun Hye [Bucheon Hospital, Bucheon (Korea, Republic of); Roh, Yun Ho; Kim, Min Jung; Youk, Ji Hyun [Yonsei University College of Medicine, Seoul (Korea, Republic of); Yoon, Jung Hyun; Kim, Sung Hun [The Catholic University of Korea, Seoul (Korea, Republic of); Kim, You Me [Dankook University College of Medicine, Cheonan (Korea, Republic of)

    2017-07-15

    To evaluate radiology residents' performance in interpretation and comprehension of breast ultrasonographic descriptors in the Breast Imaging Reporting and Data System (BI-RADS) to suggest the adequate duration of training in breast ultrasonography. A total of 102 radiology residents working in the Department of Radiology were included in this study. They were asked to answer 16 questions about the ultrasonographic lexicon and 11 questions about the BI-RADS category. We analyzed the proportion of correct answers according to the radiology residents’ year of training and duration of breast imaging training. With respect to the duration of breast imaging training, the proportion of correct answers for lexicon descriptors ranged from 77.2% to 81.3% (p = 0.368) and the proportion of correct answers for the BI-RADS category was highest after three-four months of training compared with after one month of training (p = 0.033). The proportion of correct answers for lexicon descriptors and BI-RADS category did not differ significantly according to the year of residency training. Radiology residents' comprehension of the BI-RADS category on breast ultrasonography was not associated with their year of residency training. Based on our findings, radiology residents' assessment of the BI-RADS category was significantly improved with three-four months of training compared with one month of training.

  7. Assessing Scientific Performance.

    Science.gov (United States)

    Weiner, John M.; And Others

    1984-01-01

    A method for assessing scientific performance based on relationships displayed numerically in published documents is proposed and illustrated using published documents in pediatric oncology for the period 1979-1982. Contributions of a major clinical investigations group, the Childrens Cancer Study Group, are analyzed. Twenty-nine references are…

  8. Concerns in assessing radiological releases to a major estuary

    International Nuclear Information System (INIS)

    Foldesi, Leslie P.

    1989-01-01

    Full text: In the State of Virginia, the James River flows into the Chesapeake Bay and from the mouth of the James River to the fall line the river is under the influence of tidal forces. There are several centers of commerce along the river including an international port of call at the mouth of the James. Associated with the centers of commerce are potential sources of radioactive materials for being released to the river. Two hundred miles inland, the Babcock and Wilcox nuclear fuels processing plants are situated along-side the James River, which has been known to flood its banks quickly in the mountainous regions of Virginia. Storage tanks have been swept downstream from this facility in a previous flood. Fortunately, the tanks were not destroyed. Another source of a possible release is the Suny Nuclear Power Station located on the James River about fifty miles from the Chesapeake Bay. In the cities of Norfolk and Newport News, shipyards are fueling and defueling the Navy's nuclear powered fleet. In addition, many of the Navy's ships are carrying nuclear weapons. These activities may also result in an inadvertent release. In assessing the radiological release from any one of the previously mentioned activities, it is obvious that dilution of the material released into the river is a major factor in dose assessment, as well as the fact that the water is brackish and not suitable as a source of potable water. However, dilution in this case may not be the simple solution. We also have to remember that this estuary is under tidal effects, which means that the materials may not be going out to sea to be further diluted as quickly as we would like to think. It may be possible that the material will be carried up river as far as the fall line and deposited, or deposited along the river's banks. From Virginia's experience with the pesticide, Kepone, materials may be deposited along the estuary and enter the food chain thereby necessitating the limitation of taking

  9. Concerns in assessing radiological releases to a major estuary

    Energy Technology Data Exchange (ETDEWEB)

    Foldesi, Leslie P [Virginia Department of Health, Bureau of Radiological Health, Richmond, VA (United States)

    1989-09-01

    Full text: In the State of Virginia, the James River flows into the Chesapeake Bay and from the mouth of the James River to the fall line the river is under the influence of tidal forces. There are several centers of commerce along the river including an international port of call at the mouth of the James. Associated with the centers of commerce are potential sources of radioactive materials for being released to the river. Two hundred miles inland, the Babcock and Wilcox nuclear fuels processing plants are situated along-side the James River, which has been known to flood its banks quickly in the mountainous regions of Virginia. Storage tanks have been swept downstream from this facility in a previous flood. Fortunately, the tanks were not destroyed. Another source of a possible release is the Suny Nuclear Power Station located on the James River about fifty miles from the Chesapeake Bay. In the cities of Norfolk and Newport News, shipyards are fueling and defueling the Navy's nuclear powered fleet. In addition, many of the Navy's ships are carrying nuclear weapons. These activities may also result in an inadvertent release. In assessing the radiological release from any one of the previously mentioned activities, it is obvious that dilution of the material released into the river is a major factor in dose assessment, as well as the fact that the water is brackish and not suitable as a source of potable water. However, dilution in this case may not be the simple solution. We also have to remember that this estuary is under tidal effects, which means that the materials may not be going out to sea to be further diluted as quickly as we would like to think. It may be possible that the material will be carried up river as far as the fall line and deposited, or deposited along the river's banks. From Virginia's experience with the pesticide, Kepone, materials may be deposited along the estuary and enter the food chain thereby necessitating the limitation of taking

  10. 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

  11. 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

  12. Performance assessment calculational exercises

    International Nuclear Information System (INIS)

    Barnard, R.W.; Dockery, H.A.

    1990-01-01

    The Performance Assessment Calculational Exercises (PACE) are an ongoing effort coordinated by Yucca Mountain Project Office. The objectives of fiscal year 1990 work, termed PACE-90, as outlined in the Department of Energy Performance Assessment (PA) Implementation Plan were to develop PA capabilities among Yucca Mountain Project (YMP) participants by calculating performance of a Yucca Mountain (YM) repository under ''expected'' and also ''disturbed'' conditions, to identify critical elements and processes necessary to assess the performance of YM, and to perform sensitivity studies on key parameters. It was expected that the PACE problems would aid in development of conceptual models and eventual evaluation of site data. The PACE-90 participants calculated transport of a selected set of radionuclides through a portion of Yucca Mountain for a period of 100,000 years. Results include analyses of fluid-flow profiles, development of a source term for radionuclide release, and simulations of contaminant transport in the fluid-flow field. Later work included development of a problem definition for perturbations to the originally modeled conditions and for some parametric sensitivity studies. 3 refs

  13. Context for performance assessment

    International Nuclear Information System (INIS)

    Kocher, D.C.

    1997-01-01

    In developing its recommendations on performance assessment for disposal of low-level radioactive waste, Scientific committee 87-3 of the National Council on Radiation Protection and Measurements (NCRP) has considered a number of topics that provide a context for the development of suitable approaches to performance assessment. This paper summarizes the Committee' discussions on these topics, including (1) the definition of low-level waste and its sources and properties, as they affect the variety of wastes that must be considered, (2) fundamental objectives and principles of radioactive waste disposal and their application to low-level waste, (3) current performance objectives for low-level waste disposal in the US, with particular emphasis on such unresolved issues of importance to performance assessment as the time frame for compliance, requirements for protection of groundwater and surface water, inclusion of doses from radon, demonstrating compliance with fixed performance objectives using highly uncertain model projections, and application of the principle that releases to the environment should be maintained as low as reasonably achievable (ALARA), (4) the role of active and passive institutional controls over disposal sites, (5) the role of the inadvertent human intruder in low-level waste disposal, (6) model validation and confidence in model outcomes, and (7) the concept of reasonable assurance of compliance

  14. 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

  15. 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

  16. 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

  17. Radiological risk assessment of Capstone depleted uranium aerosols.

    Science.gov (United States)

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

    2009-03-01

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

  18. Energy performance assessment methodology

    Energy Technology Data Exchange (ETDEWEB)

    Platzer, W.J. [Fraunhofer Inst. for Solar Energy Systems, Freiburg (Germany)

    2006-01-15

    The energy performance of buildings are intimately connected to the energy performance of building envelopes. The better we understand the relation between the quality of the envelope and the energy consumption of the building, the better we can improve both. We have to consider not only heating but all service energies related to the human comfort in the building, such as cooling, ventilation, lighting as well. The complexity coming from this embracing approach is not to be underestimated. It is less and less possible to realted simple characteristic performance indicators of building envelopes (such as the U-value) to the overall energy performance. On the one hand much more paramters (e.g. light transmittance) come into the picture we have to assess the product quality in a multidimensional world. Secondly buildings more and more have to work on a narrow optimum: For an old, badly insulated building all solar gains are useful for a high-performance building with very good insulation and heat recovery systems in the ventilation overheating becomes more likely. Thus we have to control the solar gains, and sometimes we need high gains, sometimes low ones. And thirdly we see that the technology within the building and the user patterns and interactions as well influence the performance of a building envelope. The aim of this project within IEA Task27 was to improve our knowledge on the complex situation and also to give a principal approach how to assess the performance of the building envelope. The participants have contributed to this aim not pretending that we have reached the end. (au)

  19. 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)

  20. A Vertically Integrated Online Radiology Curriculum Developed as a Cognitive Apprenticeship: Impact on Student Performance and Learning.

    Science.gov (United States)

    Lim-Dunham, Jennifer E; Ensminger, David C; McNulty, John A; Hoyt, Amy E; Chandrasekhar, Arcot J

    2016-02-01

    The principles of Collins' cognitive apprenticeship model were used to design a radiology curriculum in which medical students practice radiological skills using online case-based modules. The modules are embedded within clinical third-year clerkships, and students are provided with personalized feedback from the instructors. We describe the development of the vertical online radiology curriculum and evaluate its impact on student achievement and learning process using a mixed method approach. The curriculum was developed over a 2-year period. Student participation was voluntary in the first year and mandatory in the second year. For quantitative curriculum evaluation, student metrics for voluntary versus mandatory groups were assessed using independent sample t tests and variable entry method regression analysis. For qualitative analysis, responses from a survey of students about the value of the curriculum were organized into defined themes using consensus coding. Mandatory participation significantly improved (p = .001) the mean radiology examination score (82 %) compared to the voluntary group (73%), suggesting that mandatory participation had a beneficial effect on student performance. Potential preexisting differences in underlying general academic performance were accounted for by including mean basic science grades as the first variable in the regression model. The significant increase in R(2) from .16 to .28 when number of radiology cases completed was added to the original model, and the greater value of the standardized beta for this variable, suggest that the curriculum made a significant contribution to students' radiology examination scores beyond their baseline academic performance. Five dominant themes about curricular characteristics that enhanced student learning and beneficial outcomes emerged from consensus coding. These themes were (1) self-paced design, (2) receiving feedback from faculty, (3) clinical relevance of cases, (4) gaining

  1. Radiological Assessment for the Vance Road Facility Source Vault, Oak Ridge Institute for Science and Education, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Morton, J. R.

    2000-01-01

    From the 1950s, the Vance Road laboratories had been used for a broad range of nuclear medicine research involving numerous radionuclides. These radionuclides were stored in the a source vault located on the first floor of the facility. The Environmental Survey and Site Assessment Program (ESSAP) of ORISE performed a radiological assessment survey of the source vault after it had been remediated and in preparation for converting the area to office space

  2. 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

  3. Key Performance Indicators in Radiology: You Can't Manage What You Can't Measure.

    Science.gov (United States)

    Harvey, H Benjamin; Hassanzadeh, Elmira; Aran, Shima; Rosenthal, Daniel I; Thrall, James H; Abujudeh, Hani H

    2016-01-01

    Quality assurance (QA) is a fundamental component of every successful radiology operation. A radiology QA program must be able to efficiently and effectively monitor and respond to quality problems. However, as radiology QA has expanded into the depths of radiology operations, the task of defining and measuring quality has become more difficult. Key performance indicators (KPIs) are highly valuable data points and measurement tools that can be used to monitor and evaluate the quality of services provided by a radiology operation. As such, KPIs empower a radiology QA program to bridge normative understandings of health care quality with on-the-ground quality management. This review introduces the importance of KPIs in health care QA, a framework for structuring KPIs, a method to identify and tailor KPIs, and strategies to analyze and communicate KPI data that would drive process improvement. Adopting a KPI-driven QA program is both good for patient care and allows a radiology operation to demonstrate measurable value to other health care stakeholders. Copyright © 2015 Mosby, Inc. All rights reserved.

  4. 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)

  5. Radiological Assessment Of The Uterus And Fallopian Tubes In ...

    African Journals Online (AJOL)

    Objectives: This study is aimed at determining the pattern of abnormalities in the Hysterosalpingograms of patients who attended the Radiology Unit of Ebonyi State University Teaching Hospital, Abakaliki. Method: The 188 hysterosalpingograms conducted between January 2002 to December 2005 were analysed. Results: ...

  6. Medical Student Assessment of Videotape for Teaching in Diagnostic Radiology

    Science.gov (United States)

    Moss, J. R.; McLachlan, M. S. F.

    1976-01-01

    A series of six recordings that describe some aspects of the radiology of the chest, using only radiographs, were viewed by a small group of final year medical students. Their scores for factual questions immediately afterwards were compared with their attitudes to the learning experience; higher scores correlated with positive attitudes. (LBH)

  7. 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.

  8. Waste package performance assessment

    International Nuclear Information System (INIS)

    Lester, D.H.

    1981-01-01

    This paper describes work undertaken to assess the life-expectancy and post-failure nuclide release behavior of high-level and waste packages in a geologic repository. The work involved integrating models of individual phenomena (such as heat transfer, corrosion, package deformation, and nuclide transport) and using existing data to make estimates of post-emplacement behavior of waste packages. A package performance assessment code was developed to predict time to package failure in a flooded repository and subsequent transport of nuclides out of the leaking package. The model has been used to evaluate preliminary package designs. The results indicate, that within the limitation of model assumptions and data base, packages lasting a few hundreds of years could be developed. Very long lived packages may be possible but more comprehensive data are needed to confirm this

  9. Radiological assessment around CYCERON; Bilan radiologique autour de CYCERON

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-03-15

    In the frame of a radiological assessment around the medical research center of Cyceron located at Caen, the A.C.R.O. has realised at the end of 2003 a study defined by three approaches: to make an inventory of the gamma emitter radioisotopes present in the different compartments of the environment; to check outside the building, the level of exposure due to the gamma radiation; to check outside the building, the level of exposure due to the neutrons emitted during a session of production of radionuclides with the cyclotron. The analysis made on soils put in evidence the presence at significant levels, of cesium 137 ({sup 137}Cs), fission product of thirty years period. The presence of {sup 137}Cs does not come from the Cyceron activities, the cyclotron cannot create fission products. In fact, this radioisotope has for origin, the atmospheric tests of nuclear weapons made in the past, and the accident occurring at the Chernobylsk power plant in 1986. The levels are varying from some becquerels by kilogram of dry matter to a decade of becquerels by kilogram of dry matter. For the natural radioactivity the results are in compliance with those expected. Independently of the functioning of the installation, we observe an increase of the ambient gamma radiation only near radioactive waste storage. It result of the storage of the former cyclotron elements. The induced increase is moderated because at 5 meters the values do not exceed the background noise. In relation with the functioning of the installation an increase of the ambient gamma radiation is noticed. Two causes are to considered: the release of radionuclides in atmosphere with gaseous effluents and the radiance of radiation sources inside the building. After the stopping of the installation (48 h at least), no increase of gamma radiation is observed. About the neutrons monitoring, the measures made during the cyclotron functioning, highlight the lack of significant overexposure around the blockhouse at the

  10. Federal Radiological Monitoring and Assessment Center Monitoring Manual Volume 2, Radiation Monitoring and Sampling

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Aerial Measurement Systems

    2012-07-31

    The FRMAC Monitoring and Sampling Manual, Volume 2 provides standard operating procedures (SOPs) for field radiation monitoring and sample collection activities that are performed by the Monitoring group during a FRMAC response to a radiological emergency.

  11. Patient-Centered Radiology Reporting: Using Online Crowdsourcing to Assess the Effectiveness of a Web-Based Interactive Radiology Report.

    Science.gov (United States)

    Short, Ryan G; Middleton, Dana; Befera, Nicholas T; Gondalia, Raj; Tailor, Tina D

    2017-11-01

    The aim of this study was to evaluate the effectiveness of a patient-centered web-based interactive mammography report. A survey was distributed on Amazon Mechanical Turk, an online crowdsourcing platform. One hundred ninety-three US women ≥18 years of age were surveyed and then randomized to one of three simulated BI-RADS ® 0 report formats: standard report, Mammography Quality Standards Act-modeled patient letter, or web-based interactive report. Survey questions assessed participants' report comprehension, satisfaction with and perception of the interpreting radiologist, and experience with the presented report. Two-tailed t tests and χ 2 tests were used to evaluate differences among groups. Participants in the interactive web-based group spent more than double the time viewing the report than the standard report group (160.0 versus 64.2 seconds, P < .001). Report comprehension scores were significantly higher for the interactive web-based and patient letter groups than the standard report group (P < .05). Scores of satisfaction with the interpreting radiologist were significantly higher for the web-based interactive report and patient letter groups than the standard report group (P < .01). There were no significant differences between the patient letter and web-based interactive report groups. Radiology report format likely influences communication effectiveness. For result communication to a non-medical patient audience, patient-centric report formats, such as a Mammography Quality Standards Act-modeled patient letter or web-based interactive report, may offer advantages over the standard radiology report. Future work is needed to determine if these findings are reproducible in patient care settings and to determine how best to optimize radiology result communication to patients. Copyright © 2017 American College of Radiology. Published by Elsevier Inc. All rights reserved.

  12. A Business Analytics Software Tool for Monitoring and Predicting Radiology Throughput Performance.

    Science.gov (United States)

    Jones, Stephen; Cournane, Seán; Sheehy, Niall; Hederman, Lucy

    2016-12-01

    Business analytics (BA) is increasingly being utilised by radiology departments to analyse and present data. It encompasses statistical analysis, forecasting and predictive modelling and is used as an umbrella term for decision support and business intelligence systems. The primary aim of this study was to determine whether utilising BA technologies could contribute towards improved decision support and resource management within radiology departments. A set of information technology requirements were identified with key stakeholders, and a prototype BA software tool was designed, developed and implemented. A qualitative evaluation of the tool was carried out through a series of semi-structured interviews with key stakeholders. Feedback was collated, and emergent themes were identified. The results indicated that BA software applications can provide visibility of radiology performance data across all time horizons. The study demonstrated that the tool could potentially assist with improving operational efficiencies and management of radiology resources.

  13. Fine tuning of work practices of common radiological investigations performed using computed radiography system

    International Nuclear Information System (INIS)

    Livingstone, Roshan S.; Timothy Peace, B.S.; Sunny, S.; Victor Raj, D.

    2007-01-01

    Introduction: The advent of the computed radiography (CR) has brought about remarkable changes in the field of diagnostic radiology. A relatively large cross-section of the human population is exposed to ionizing radiation on account of common radiological investigations. This study is intended to audit radiation doses imparted to patients during common radiological investigations involving the use of CR systems. Method: The entrance surface doses (ESD) were measured using thermoluminescent dosimeters (TLD) for various radiological investigations performed using the computed radiography (CR) systems. Optimization of radiographic techniques and radiation doses was done by fine tuning the work practices. Results and conclusion: Reduction of radiation doses as high as 47% was achieved during certain investigations with the use of optimized exposure factors and fine-tuned work practices

  14. Radiological assessment of depleted uranium migration offsite from an ordnance range

    International Nuclear Information System (INIS)

    Rynders, D.G.

    1996-01-01

    The military utilizes ordnance loaded with depleted uranium in order to maximize armor penetrating capabilities. These weapons are tested on open ranges where the weapons are fired through a cloth target and impact into the soil. This paper examines the potential environmental impact from use of depleted uranium in an open setting. A preliminary pathway analysis was performed to examine potential routes of exposure to nonhuman species in the vicinity and ultimately to man. Generic data was used in the study to estimate the isotopic mix and weight of the ordnance. Key factors in the analysis included analyzing the physics of weapon impact on soil, chemical changes in material upon impact, and mechanisms of offsite transport (including atmospheric and overland transport). Non-standard exposure scenarios were investigated, including the possibility of offsite contaminant transport due to range grassfires. Two radiological assessment codes, MEPAS (Multi media Environmental Pollutant Assessment System) and RESRAD were used to help analyze the scenarios

  15. Idaho National Engineering Laboratory Radiological Control performance indicator report: First quarter, calendar year 1995

    International Nuclear Information System (INIS)

    Aitken, S.B.

    1995-07-01

    The INEL Radiological Control Performance Indicator Report is provided quarterly, inaccordance with Article 133 of the INEL Radiological Control Manual. Indicators are used as a measure of performance of the Radiological Control Program and as a motivation for improvement, not as a goal in themselves. These indicators should be used by management to assist in focusing priorities and attention and adherence to As-Low-As-Reasonably-Achievable (ALARA) practices. The ALARA Committees establish ALARA goals for the INEL based on forecasts and goals provided by each facility organizational manager or supervisor.Performance goals are realistic and measurable. Stringent goals are set at least annually to reflect expected workloads and improvement of radiological performance. Goals higher than previous goals may occasionally be set due to changes in work scope or mission. The INEL Radiological Control Performance Indicators consist of: Collective dose in person-rem; average worker dose, maximum dose to a worker, and maximum neutron dose to a worker;the number of skin and clothing contaminations, including the number of contaminated wounds and facial contaminations; the number of radioactive material intakes; the area of Contamination, High Contamination, and Airborne Radioactivity Areas in square feet; and airborne radioactivity events and spills

  16. 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.)

  17. TURVA-2012: Performance assessment

    International Nuclear Information System (INIS)

    Hellae, Pirjo; Snellman, Margit; Marcos, Nuria; Pastina, Barbara; Smith, Paul; Koskinen, Kari

    2014-01-01

    TURVA-2012 is Posiva's safety case in support of the Preliminary Safety Analysis Report (PSAR) and application for a construction licence for a repository for disposal of spent nuclear fuel at the Olkiluoto site in south-western Finland. Posiva's safety concept is based on long-term isolation and containment, which is achieved through a robust engineered barrier system (EBS) design and favourable geological conditions at the repository site. The reference design considered in the TURVA-2012 safety case is the KBS-3V design, with the EBS consisting of a copper-iron canister, a buffer of swelling clay material, a backfill in the deposition tunnels of low-permeability material and closure of the central tunnels and other underground openings. The host rock acts as a natural barrier. Each barrier contributes to safety through one or more safety function. The conditions needed for the barriers to fulfil their respective safety functions are expressed in terms of performance targets for the EBS and the target properties for the host rock. The performance assessment (Posiva, 2013), which is a key component of TURVA-2012, analyses the ability of the repository system to provide containment and isolation of the spent nuclear fuel during the long-term evolution of the system and the site. The conditions needed for the barriers to fulfil their respective safety functions are expressed in terms of performance targets for the engineered barriers and target properties for the host rock, for example properties related to the corrosion resistance and mechanical strength of the canister as well as groundwater flow and composition. The analyses take into account the uncertainties in the initial state, the subsequent thermal, hydraulic, mechanical and chemical evolution of the repository system and uncertainties in the evolution. The conclusions of the performance assessment are based mostly on the output of key modelling activities. Whenever modelling is not possible the conclusions

  18. 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.

  19. Assessment of radiological and non-radiological hazards in the nuclear fuel cycle - The Indian experience

    International Nuclear Information System (INIS)

    Krishnamony, S.; Gopinath, D.V.

    1996-01-01

    Design and operational aspects of nuclear fuel cycle facilities have several features that distinguish them from nuclear power plants. These are related to (i) the nature of operations which are chiefly mining, metallurgical and chemical; (ii) the nature and type of radio-active materials handled, their specific activities and inventories; and (iii) the physical and chemical processes involved and the associated containment provisions. Generally the radioactive materials are present in an already highly dispersible or mobile form, in the form of solutions, slurries and powders, often associated with a wide variety of reactive and corrosive chemicals. There are further marked differences between the front-end and back-end of the fuel cycle. Whereas the front-end is characterized by the presence of large quantities of low specific activity naturally occurring radioactive materials, the back-end is characterized by high specific activities and concentrations of fission products and actinides. Radioactive characteristics of waste arisings are also different in different phases of the nuclear fuel cycle. Potential for internal exposure in the occupational environment is another distinguishing feature as compared with the more common designs of nuclear power reactors. Potential for accidents, their phenomenology and the resulting consequences are also markedly different in fuel cycle operations. The non-radiological hazards in fuel cycle operations are also of significance, since the operations are mostly mining, metallurgical and chemical in nature. These aspects are examined and evaluated in this paper, based on the Indian experience. (author). 12 refs, 10 tabs

  20. 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

  1. 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.)

  2. 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

  3. 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

  4. Radiological site assessment at sun rose claim utilizing ScanPlot{sup SM} technology

    Energy Technology Data Exchange (ETDEWEB)

    Downey, H., E-mail: heath.downey@amecfw.com [Amec Foster Wheeler, Portland, ME (United States)

    2015-07-01

    ScanPlot{sup SM} gamma spectroscopy land survey system was utilized for the overland survey of uranium at the Sun Rose Claim in the Northwest Territories. The Sun Rose Claim is a former uranium exploration site and previous investigations had identified uranium ore and waste rock. ScanPlot{sup SM} radiological scan surveys were performed utilizing a backpack system. ScanPlot{sup SM} platform utilized spectroscopy grade sodium iodide detectors configured for optimal spatial coverage and radiation detection. Survey locations were recorded using an on-board global positioning system (GPS). The radiological spectral data from the radiation detectors is automatically logged and linked with the GPS coordinates to an on-board computer to create isocontour figures using a color scale to represent radioactivity levels. The advantage of utilizing the ScanPlot{sup SM} system for this assessment is that the nature and extent of uranium is provided without having to collect and assay a large number of samples. (author)

  5. Relationship Between Dental Hygiene Students' Performance in an Oral Radiology Course and the National Board Dental Hygiene Examination: A Retrospective Study.

    Science.gov (United States)

    Liang, Hui; DeWald, Janice P; Solomon, Eric S

    2018-02-01

    Dental hygiene students' performance in oral radiology courses may give an early indication of their readiness prior to taking the National Board Dental Hygiene Examination (NBDHE). The aim of this study was to determine the relationship between dental hygiene students' performance in an oral radiology lecture course and their performance on the NBDHE. Data were collected for all 117 dental hygiene students at Texas A&M University College of Dentistry from 2006 to 2009 who took the NBDHE during their second year of the program. Their final grades and scores on three written section examinations in an oral radiology course taken in their first year were compared with their overall NBDHE scores and raw scores on the oral radiology and case study sections. Moderate correlations (0.3radiology course, with the strongest correlation with the final grade (r=0.488, pradiology, followed by scores in anatomic sciences; the weakest relationship was with scores in pharmacology. This relationship can help identify students who may need extra support in the oral radiology course and other courses to prepare them to succeed when they take the NBDHE. This study also contributes to understanding of the general relationship between dental hygiene program courses and students' success on the clinical licensing exam and will hopefully encourage other programs to assess their students' performance in this way.

  6. Federal Radiological Monitoring and Assessment Center Health and Safety Manual

    Energy Technology Data Exchange (ETDEWEB)

    FRMAC Health and Safety Working Group

    2012-03-20

    This manual is a tool to provide information to all responders and emergency planners and is suggested as a starting point for all organizations that provide personnel/assets for radiological emergency response. It defines the safety requirements for the protection of all emergency responders. The intent is to comply with appropriate regulations or provide an equal level of protection when the situation makes it necessary to deviate. In the event a situation arises which is not addressed in the manual, an appropriate management-level expert will define alternate requirements based on the specifics of the emergency situation. This manual is not intended to pertain to the general public.

  7. 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

  8. 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)

  9. Evaluation of radiological safety assessment of a repository in a clay rock formation

    International Nuclear Information System (INIS)

    1999-01-01

    This report presents a comprehensive description of the post-closure radiological safety assessment of a repository for the spent fuel arisings resulting from the Spanish nuclear program excavated in a clay host rock formation. In this report three scenarios have been analysed in detail. The first scenario represents the normal in detail. The first scenario represents the normal evolution of the repository (Reference Scenario); and includes a set of variants to investigate the relative importance of the various repository components and examine the sensitivity of the performance to parameters variations. Two altered scenarios have also been considered: deep well construction and poor sealing of the repository. This document contains a detailed description of the repository system, the methodology adopted for the scenarios generation, the process modelling approach and the results of the consequences analysis. (Author)

  10. Radiological and chemical assessment of phosphate rocks in some countries

    International Nuclear Information System (INIS)

    Cevik, U.; Baltas, H.; Tabak, A.; Damla, N.

    2010-01-01

    In this study, the radiological, structural and chemical characterizations of Mardin-Mazidagi phosphate rock, which is an important phosphate fertilizer source in Turkey were investigated and compared to those of several different phosphate rocks of Tunisia, Egypt, Morocco, Algeria and Syria using gamma spectrometry, X-ray diffraction (XRD) and X-ray fluorescence (XRF) measurement techniques. Elemental analysis results of phosphate samples showed that they were mainly composed of CaO, P 2 O 5 , SiO 2 , Al 2 O 3 , SO 3 and Fe 2 O 3 . Elemental concentrations of U and Th were calculated using 226 Ra and 232 Th activity concentrations, respectively. As a result of XRD analysis, the main peaks of the samples were found to be Fluorapatite (Ca 5 (PO 4 ) 3 F). The radioactivity concentration levels for 226 Ra, 232 Th and 40 K in all phosphate samples ranged from 250 to 1029 Bq kg -1 with a mean of 535 Bq kg -1 , from 5 to 50 Bq kg -1 with a mean of 20 Bq kg -1 and from 117 to 186 Bq kg -1 with a mean of 148 Bq kg -1 , respectively. The computed values of annual effective doses ranged from 0.17 to 0.59 mSv, with a mean value of 0.33 mSv, which is lower than the recommended limit of 1 mSv y -1 by the International Commission on Radiological Protection.

  11. 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

  12. 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.)

  13. 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.)

  14. Georgia's Teacher Performance Assessment

    Science.gov (United States)

    Fenton, Anne Marie; Wetherington, Pamela

    2016-01-01

    Like most states, Georgia until recently depended on an assessment of content knowledge to award teaching licenses, along with a licensure recommendation from candidates' educator preparation programs. While the content assessment reflected candidates' grasp of subject matter, licensure decisions did not hinge on direct, statewide assessment of…

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

    International Nuclear Information System (INIS)

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

    1995-01-01

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

  16. 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)

  17. 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

  18. An honest day's work: pay for performance in a pediatric radiology department

    International Nuclear Information System (INIS)

    Bisset, George S.

    2017-01-01

    Compensation models in radiology take a variety of forms, but regardless of practice type, successful models must reward productivity, be simple, and epitomize fairness. The ideal model should also be flexible enough to transition, based upon the changing strategic goals of a department. The plan should be constructed around rewarding the behaviors that the organization values. In this minisymposium article the author presents the value of different types of compensation plans and discusses advantages and disadvantages. Finally, the author presents a pay-for-performance model that has had long-term success at a private-turned-academic practice in pediatric radiology. (orig.)

  19. An honest day's work: pay for performance in a pediatric radiology department

    Energy Technology Data Exchange (ETDEWEB)

    Bisset, George S. [Texas Children' s Hospital, Department of Radiology, Baylor College of Medicine, Houston, TX (United States)

    2017-06-15

    Compensation models in radiology take a variety of forms, but regardless of practice type, successful models must reward productivity, be simple, and epitomize fairness. The ideal model should also be flexible enough to transition, based upon the changing strategic goals of a department. The plan should be constructed around rewarding the behaviors that the organization values. In this minisymposium article the author presents the value of different types of compensation plans and discusses advantages and disadvantages. Finally, the author presents a pay-for-performance model that has had long-term success at a private-turned-academic practice in pediatric radiology. (orig.)

  20. Radiological impact assessment of the rehabilitated Nabarlek uranium minesite

    International Nuclear Information System (INIS)

    Martin, P.; Tims, S.; Ryan, B.; Prendergast, B.

    1998-01-01

    Full text: Nabarlek was a small high-grade uranium deposit located in Arnhem Land in the Northern Territory of Australia. Queensland Mines Ltd mined the deposit in 1979 and subsequently milled the ore between 1981 and 1988. Major rehabilitation and decommissioning works were completed at the end of 1995. In 1996 ERISS began a detailed radiological study of the Nabarlek site. Initial work has included an airborne radiometric survey, a ground-based gamma dose rate survey, collection of meteorological data, and measurement of radon emanation rate from the ground, radon concentrations in air, and long-lived radionuclide concentrations in surface soil and groundwater. This talk will give an overview of the study, with an emphasis on the results of the airborne radiometric survey and corresponding ground-based measurements

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

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  2. A review of the uncertainties in the assessment of radiological consequences of spent nuclear fuel disposal

    International Nuclear Information System (INIS)

    Wiborgh, M.; Elert, M.; Hoeglund, L.O.; Jones, C.; Grundfelt, B.; Skagius, K.; Bengtsson, A.

    1992-06-01

    Radioactive waste disposal systems for spent nuclear fuel are designed to isolate the radioactive waste from the human environment for long period of time. The isolation is provided by a combination of engineered and natural barriers. Safety assessments are performed to describe and quantify the performance of the individual barriers and the disposal system over long-term periods. These assessments will always be associated with uncertainties. Uncertainties can originate from the variability of natural systems and will also be introduced in the predictive modelling performed to quantitatively evaluate the behaviour of the disposal system as a consequence of the incomplete knowledge about the governing processes. Uncertainties in safety assessments can partly be reduced by additional measurements and research. The aim of this study has been to identify uncertainties in assessments of radiological consequences from the disposal of spent nuclear fuel based on the Swedish KBS-3 concept. The identified uncertainties have been classified with respect to their origin, i.e. in conceptual, modelling and data uncertainties. The possibilities to reduce the uncertainties are also commented upon. In assessments it is important to decrease uncertainties which are of major importance for the performance of the disposal system. These could to some extent be identified by uncertainty analysis. However, conceptual uncertainties and some type of model uncertainties are difficult to evaluate. To be able to decrease uncertainties in conceptual models, it is essential that the processes describing and influencing the radionuclide transport in the engineered and natural barriers are sufficiently understood. In this study a qualitative approach has been used. The importance of different barriers and processes are indicated by their influence on the release of some representative radionuclides. (122 refs.) (au)

  3. An automated radiological survey method for performing site remediation and decommissioning

    International Nuclear Information System (INIS)

    Handy, R.G.; Bolch, W.E.; Harder, G.F.; Tolaymat, T.M.

    1994-01-01

    A portable, computer-based method of performing environmental monitoring and assessment for site remediation and decommissioning has been developed. The integrated system has been developed to provide for survey time reductions and real-time data analysis. The technique utilizes a notebook 486 computer with the necessary hardware and software components that makes it possible to be used in an almost unlimited number of environmental monitoring and assessment scenarios. The results from a pilot, open-quotes hide-and-seekclose quotes gamma survey and an actual alpha decontamination survey were elucidated. It was found that a open-quotes hide-and-seekclose quotes survey could come up with timely and accurate conclusions about the position of the source. The use of the automated system in a Th-232 alpha survey resulted in a reduction in the standard time necessary to do a radiological survey. In addition, the ability to analyze the data on-site allowed for identification and location of areas which needed further decontamination. Finally, a discussion on possible future improvements and field conclusions was made

  4. A Combined Pharmacokinetic and Radiologic Assessment of Dynamic Contrast-Enhanced Magnetic Resonance Imaging Predicts Response to Chemoradiation in Locally Advanced Cervical Cancer

    International Nuclear Information System (INIS)

    Semple, Scott; Harry, Vanessa N. MRCOG.; Parkin, David E.; Gilbert, Fiona J.

    2009-01-01

    Purpose: To investigate the combination of pharmacokinetic and radiologic assessment of dynamic contrast-enhanced magnetic resonance imaging (MRI) as an early response indicator in women receiving chemoradiation for advanced cervical cancer. Methods and Materials: Twenty women with locally advanced cervical cancer were included in a prospective cohort study. Dynamic contrast-enhanced MRI was carried out before chemoradiation, after 2 weeks of therapy, and at the conclusion of therapy using a 1.5-T MRI scanner. Radiologic assessment of uptake parameters was obtained from resultant intensity curves. Pharmacokinetic analysis using a multicompartment model was also performed. General linear modeling was used to combine radiologic and pharmacokinetic parameters and correlated with eventual response as determined by change in MRI tumor size and conventional clinical response. A subgroup of 11 women underwent repeat pretherapy MRI to test pharmacokinetic reproducibility. Results: Pretherapy radiologic parameters and pharmacokinetic K trans correlated with response (p < 0.01). General linear modeling demonstrated that a combination of radiologic and pharmacokinetic assessments before therapy was able to predict more than 88% of variance of response. Reproducibility of pharmacokinetic modeling was confirmed. Conclusions: A combination of radiologic assessment with pharmacokinetic modeling applied to dynamic MRI before the start of chemoradiation improves the predictive power of either by more than 20%. The potential improvements in therapy response prediction using this type of combined analysis of dynamic contrast-enhanced MRI may aid in the development of more individualized, effective therapy regimens for this patient group.

  5. 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)

  6. 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)

  7. The Effects of Fatigue From Overnight Shifts on Radiology Search Patterns and Diagnostic Performance.

    Science.gov (United States)

    Hanna, Tarek N; Zygmont, Matthew E; Peterson, Ryan; Theriot, David; Shekhani, Haris; Johnson, Jamlik-Omari; Krupinski, Elizabeth A

    2018-01-20

    The aim of this study was to assess the effect of overnight shifts (ONS) on radiologist fatigue, visual search pattern, and diagnostic performance. This experimental study was approved by the institutional review board. Twelve radiologists (five faculty members and seven residents) each completed two sessions: one during a normal workday ("not fatigued") and another in the morning after an ONS ("fatigued"). Each radiologist completed the Swedish Occupational Fatigue Inventory. During each session, radiologists viewed 20 bone radiographs consisting of normal and abnormal findings. Viewing time, diagnostic confidence, and eye-tracking data were recorded. Swedish Occupational Fatigue Inventory results demonstrated worsening in all five variables (lack of energy, physical exertion, physical discomfort, lack of motivation, and sleepiness) after ONS (P radiologists were more fatigued with worse diagnostic performance, a 45% increase in view time per case, a 60% increase in total gaze fixations, and a 34% increase in time to fixate on the fracture. The effects of fatigue were more pronounced in residents. Copyright © 2017 American College of Radiology. Published by Elsevier Inc. All rights reserved.

  8. 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)

  9. 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)

  10. Methodology for performing measurements to release material from radiological control

    International Nuclear Information System (INIS)

    Durham, J.S.; Gardner, D.L.

    1993-09-01

    This report describes the existing and proposed methodologies for performing measurements of contamination prior to releasing material for uncontrolled use at the Hanford Site. The technical basis for the proposed methodology, a modification to the existing contamination survey protocol, is also described. The modified methodology, which includes a large-area swipe followed by a statistical survey, can be used to survey material that is unlikely to be contaminated for release to controlled and uncontrolled areas. The material evaluation procedure that is used to determine the likelihood of contamination is also described

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

    Science.gov (United States)

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

    1997-07-01

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

  12. OLEM Performance Assessment Information

    Data.gov (United States)

    U.S. Environmental Protection Agency — This asset includes a variety of data sets that measure the performance of Office of Land and Emergency Management (OLEM) programs in support of the Office of the...

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

    International Nuclear Information System (INIS)

    Zajacova, Z.

    2009-01-01

    The dissertation addressed three complex radiological issues of the ATLAS experiment at the LHC. Extensive scientific study of the detector activation was performed in order to delineate its radioactive waste zoning. This work involved two independent calculations. One was performed by folding particle fluxes obtained from the GCALOR Monte Carlo radiation transport code with radionuclide production cross sections and the other was done by scoring residual nuclei production with the FLUKA Monte Carlo radiation transport code. In terms of the radioactive waste zoning the results of the two calculations were mutually supportive and in good agreement. To cross-check them on a more detailed level we performed a dedicated study. The cross-check revealed that for most radionuclides the predictions of the two methods are in a very good agreement, within a factor of 2. The production of certain important radionuclides from copper was about 3 times higher by the folding method than with FLUKA. This effect was attributed to the Silberberg- Tsao cross-sections that were used for the folding calculations. Indeed the results were in a better agreement when a different set of cross sections, compiled from predominantly experimental sources, was used. Finally, the largest systematic discrepancies between the two methods were found for the production of 65 Zn in copper 183 Re in tungsten and 56 Co in iron, which was higher with the folding method by more than a factor of 5 for 5 6Co and more than a factor of 20 for the others. These radionuclides are produced almost exclusively by protons through 65 C(p;n) 65 Zn, 56 Fe(p; n) 56 Co and 183 W(p; n) 183 Re reactions. The folding method relied on the Silberberg-Tsao cross sections and consequently treated all hadrons effectively as protons. However, in the end-cap calorimeter protons account for less than 20% of the total hadron flux (not counting neutrons below 20 MeV). Since the contribution of these radionuclides to the total

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-09-15

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

  15. Radiological safety assessment inside ancient Egyptian tombs in Saqqara.

    Science.gov (United States)

    El-Kameesy, S U; Salama, E; El-Fiki, S A; Ehab, M; Rühm, W

    2016-12-01

    Many archaeological sites in Egypt are unique worldwide, such as ancient tombs and pyramids, because they document fundamental developments in human civilization that took place several thousands of years ago. For this reason, these sites are visited by numerous visitors every year. The present work is devoted to provide a pre-operational radiological baseline needed to quantify occupational radiation exposure at the famous Saqqara region in Cairo, Egypt. A hyperpure Ge detector has been used in the γ-ray spectrometric analysis while the (222)Rn concentration was measured using a portable radon monitor RTM 1688-2, SARAD. The mean specific activities of (226)Ra, (232)Th and (40)K in the samples collected from the interior walls of the Saqqara tombs were determined and found to show average values of 16, 8.5 and 45 Bq kg(-1), respectively. The concentration of radon was measured inside the tombs Serapeum, South tomb and the Zoser Pyramid (fifth level) and an associated average working level of 0.83 WL was obtained. In order to avoid the health hazards associated with the exposure to radon during the long period of work inside these tombs, proposed solutions are introduced.

  16. 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.

  17. Simply Performance Assessment

    Science.gov (United States)

    McLaughlin, Cheryl A.; McLaughlin, Felecia C.; Pringle, Rose M.

    2013-01-01

    This article presents the experiences of Miss Felecia McLaughlin, a fourth-grade teacher from the island of Jamaica who used the model proposed by Bass et al. (2009) to assess conceptual understanding of four of the six types of simple machines while encouraging collaboration through the creation of learning teams. Students had an opportunity to…

  18. 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)

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

    International Nuclear Information System (INIS)

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

    1982-05-01

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

  20. Total System Performance Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Yong Soo; Kang, Chul Hyung; Lee, Youn Myoung; Han, Ji Woong; Choi, Jong Won; Hahn, Pil Soo; Park, Jeong Hwa; Jeong, Mi Seon

    2007-06-15

    Based on the KAERI FEP list developed through the previous studies, the KAERI FEP Encyclopedia has been developed. Current version is 1.0 which includes all relevant FEPs to compose of two references and all alternative scenarios. Many interaction FEPs between scenario defining FEP(SDF) are created throughout the study. FEPs are classified into many Integrated FEP(IFEP) which eventually become the elements of the RES matrix. The FEAS program one of the component of the KAERI's CYPRUS information system is added to develop the FEP, RES, AC, AMF and finally scenarios. It assists to create transparent way to deal with assessment from the stage of the planning of the R and D to the final stage of the external audit and regulatory body review. Even though MASCOT-K and compartment analysis codes such as AMBER, GoldSim and Ecolego are excellent for TSPA they by in heritage possess a certain limitation especially to identify a proper migration cross sectional area when a relatively big component intersects with a tiny one such as a fracture. It is truly 3D phenomena in nature. MDPSA code is developed which is expected to overcome limitations in compartment models while successfully deals with natural disruptive events. The R and D target for the TSPA is to develop the sufficient scenarios and their variation cases to understand the safety of KRS in every possible aspect. For this, reference scenarios, alternative scenarios covering engineered barrier failure and natural events are developed and assessed respectively for around 100 cases. The stylized template to assess the Korean reference biosphere is developed using the AMBER. Three critical groups, agricultural, freshwater and marine water fishing groups are identified to assess the DCF following the guidelines of ICRP. Based on the QA principles of T2R3, the web based QA system is developed using the procedures in the USNRC 10CFR50 Appendix B. The QA system is combined with the PAID and FEAS to create the comprehensive

  1. Total System Performance Assessment

    International Nuclear Information System (INIS)

    Hwang, Yong Soo; Kang, Chul Hyung; Lee, Youn Myoung; Han, Ji Woong; Choi, Jong Won; Hahn, Pil Soo; Park, Jeong Hwa; Jeong, Mi Seon

    2007-06-01

    Based on the KAERI FEP list developed through the previous studies, the KAERI FEP Encyclopedia has been developed. Current version is 1.0 which includes all relevant FEPs to compose of two references and all alternative scenarios. Many interaction FEPs between scenario defining FEP(SDF) are created throughout the study. FEPs are classified into many Integrated FEP(IFEP) which eventually become the elements of the RES matrix. The FEAS program one of the component of the KAERI's CYPRUS information system is added to develop the FEP, RES, AC, AMF and finally scenarios. It assists to create transparent way to deal with assessment from the stage of the planning of the R and D to the final stage of the external audit and regulatory body review. Even though MASCOT-K and compartment analysis codes such as AMBER, GoldSim and Ecolego are excellent for TSPA they by in heritage possess a certain limitation especially to identify a proper migration cross sectional area when a relatively big component intersects with a tiny one such as a fracture. It is truly 3D phenomena in nature. MDPSA code is developed which is expected to overcome limitations in compartment models while successfully deals with natural disruptive events. The R and D target for the TSPA is to develop the sufficient scenarios and their variation cases to understand the safety of KRS in every possible aspect. For this, reference scenarios, alternative scenarios covering engineered barrier failure and natural events are developed and assessed respectively for around 100 cases. The stylized template to assess the Korean reference biosphere is developed using the AMBER. Three critical groups, agricultural, freshwater and marine water fishing groups are identified to assess the DCF following the guidelines of ICRP. Based on the QA principles of T2R3, the web based QA system is developed using the procedures in the USNRC 10CFR50 Appendix B. The QA system is combined with the PAID and FEAS to create the comprehensive

  2. Total System Performance Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Yong Soo; Kang, Chul Hyung; Lee, Youn Myoung; Han, Ji Woong; Choi, Jong Won; Hahn, Pil Soo; Park, Jeong Hwa; Jeong, Mi Seon

    2007-06-15

    Based on the KAERI FEP list developed through the previous studies, the KAERI FEP Encyclopedia has been developed. Current version is 1.0 which includes all relevant FEPs to compose of two references and all alternative scenarios. Many interaction FEPs between scenario defining FEP(SDF) are created throughout the study. FEPs are classified into many Integrated FEP(IFEP) which eventually become the elements of the RES matrix. The FEAS program one of the component of the KAERI's CYPRUS information system is added to develop the FEP, RES, AC, AMF and finally scenarios. It assists to create transparent way to deal with assessment from the stage of the planning of the R and D to the final stage of the external audit and regulatory body review. Even though MASCOT-K and compartment analysis codes such as AMBER, GoldSim and Ecolego are excellent for TSPA they by in heritage possess a certain limitation especially to identify a proper migration cross sectional area when a relatively big component intersects with a tiny one such as a fracture. It is truly 3D phenomena in nature. MDPSA code is developed which is expected to overcome limitations in compartment models while successfully deals with natural disruptive events. The R and D target for the TSPA is to develop the sufficient scenarios and their variation cases to understand the safety of KRS in every possible aspect. For this, reference scenarios, alternative scenarios covering engineered barrier failure and natural events are developed and assessed respectively for around 100 cases. The stylized template to assess the Korean reference biosphere is developed using the AMBER. Three critical groups, agricultural, freshwater and marine water fishing groups are identified to assess the DCF following the guidelines of ICRP. Based on the QA principles of T2R3, the web based QA system is developed using the procedures in the USNRC 10CFR50 Appendix B. The QA system is combined with the PAID and FEAS to create the

  3. DOEZOR2: a code to assess the radiological impact of effluent discharges

    International Nuclear Information System (INIS)

    Martin Garcia, J.E.; Gomez Rodriguez, C.A.; Gimeno Blesa, M.E.; GARCIA ACOSTA, F.

    2010-01-01

    DOEZOR2 (DOsis al Exterior en ZORita v. 2) comprises a suite of models and data management tools which can be used to perform the radiological impact assessments of routine and continuous discharges from nuclear power plants and nuclear fuel cycle facilities for regulatory purposes. The Code is based on Radiation Protection 72 and the Regulatory Guide 1.109 (USNRC) methodology. The code development was carried out by SOCOIN (Gas Natural Fenosa Group) and is implemented in Jose Cabrera NPP (or Zorita NPP). DOEZOR has been operating during ten years and is about to be updated in order to consider realistic doses methodology. The new software differs from its predecessor in a number of ways, including a new user interface, new radionuclides and several new capacities (realistic dose). The model is developed to estimate radiological consequences of emissions from nuclear power plants. Internal exposure via inhalation and ingestion, external exposure from clouds and radioactivity deposited on the ground are included in the model. DOEZOR2 has been developed in Visual Fortran, using user friendly windows environment and modular architecture (easy to implement for other uses and installations). The main features of the code include: - Annual discharge to the atmospheric or river environment can be modelled. - Dynamic systems dispersion of radionuclides released to the river (two reservoirs). - A comprehensive list of exposure pathways. - A suite of environmental transfer models to estimate the transfer of radionuclides through the environment. - Site specific data (parameters of life habits). - Results in terms of individual doses (three age's groups), using effective dose as defined in Council Directive 96/29/EURATOM and dose coefficients from U.S. Federal Guidance Report 13. - Results in 'MS Word form' for periodic information to authorities. This software could be implemented anywhere, considering the particular characteristic of the site for the plant or facility

  4. Radiological analyses of France Telecom surge arresters. Study performed for the CGT FAPT Cantal

    International Nuclear Information System (INIS)

    2010-02-01

    This document reports the radiological characterization of various versions of surge arresters used in the past to protect telephone lines against over-voltages. These equipment, which use various radioactive materials, were assessed by gamma radiation flow measurements, alpha-beta-gamma count rate measurements, dose rate measurements, gamma spectrometry analyses, tritium emanation test, radon 222 emanation test, smearing. Recommendations are formulated to manage radioactive surge arresters which are still being operated

  5. The process of performance assessment

    International Nuclear Information System (INIS)

    King, C.M.; Halford, D.K.

    1986-01-01

    An introductory review of the subject of ''Performance Assessment'' will be presented. Emphasis will be placed on the process of performance assessment from the standpoint of defining the process. Performance assessment, from evolving experience at DOE sites, has short-term and long-term subprograms, the components of which will be discussed. The role of mathematical modeling in performance assessment will be addressed including the pros and cons of current approaches. Finally, the ''system/site/technology'' issues as the focal point of this symposium will be reviewed

  6. Technology Performance Level Assessment Methodology.

    Energy Technology Data Exchange (ETDEWEB)

    Roberts, Jesse D.; Bull, Diana L; Malins, Robert Joseph; Costello, Ronan Patrick; Aurelien Babarit; Kim Nielsen; Claudio Bittencourt Ferreira; Ben Kennedy; Kathryn Dykes; Jochem Weber

    2017-04-01

    The technology performance level (TPL) assessments can be applied at all technology development stages and associated technology readiness levels (TRLs). Even, and particularly, at low TRLs the TPL assessment is very effective as it, holistically, considers a wide range of WEC attributes that determine the techno-economic performance potential of the WEC farm when fully developed for commercial operation. The TPL assessment also highlights potential showstoppers at the earliest possible stage of the WEC technology development. Hence, the TPL assessment identifies the technology independent “performance requirements.” In order to achieve a successful solution, the entirety of the performance requirements within the TPL must be considered because, in the end, all the stakeholder needs must be achieved. The basis for performing a TPL assessment comes from the information provided in a dedicated format, the Technical Submission Form (TSF). The TSF requests information from the WEC developer that is required to answer the questions posed in the TPL assessment document.

  7. 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.

  8. How visual search relates to visual diagnostic performance: a narrative systematic review of eye-tracking research in radiology.

    Science.gov (United States)

    van der Gijp, A; Ravesloot, C J; Jarodzka, H; van der Schaaf, M F; van der Schaaf, I C; van Schaik, J P J; Ten Cate, Th J

    2017-08-01

    Eye tracking research has been conducted for decades to gain understanding of visual diagnosis such as in radiology. For educational purposes, it is important to identify visual search patterns that are related to high perceptual performance and to identify effective teaching strategies. This review of eye-tracking literature in the radiology domain aims to identify visual search patterns associated with high perceptual performance. Databases PubMed, EMBASE, ERIC, PsycINFO, Scopus and Web of Science were searched using 'visual perception' OR 'eye tracking' AND 'radiology' and synonyms. Two authors independently screened search results and included eye tracking studies concerning visual skills in radiology published between January 1, 1994 and July 31, 2015. Two authors independently assessed study quality with the Medical Education Research Study Quality Instrument, and extracted study data with respect to design, participant and task characteristics, and variables. A thematic analysis was conducted to extract and arrange study results, and a textual narrative synthesis was applied for data integration and interpretation. The search resulted in 22 relevant full-text articles. Thematic analysis resulted in six themes that informed the relation between visual search and level of expertise: (1) time on task, (2) eye movement characteristics of experts, (3) differences in visual attention, (4) visual search patterns, (5) search patterns in cross sectional stack imaging, and (6) teaching visual search strategies. Expert search was found to be characterized by a global-focal search pattern, which represents an initial global impression, followed by a detailed, focal search-to-find mode. Specific task-related search patterns, like drilling through CT scans and systematic search in chest X-rays, were found to be related to high expert levels. One study investigated teaching of visual search strategies, and did not find a significant effect on perceptual performance. Eye

  9. 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

  10. Radiological Indicators of Bone Age Assessment in Cephalometric Images. Review

    Science.gov (United States)

    Durka-Zając, Magdalena; Mituś-Kenig, Maria; Derwich, Marcin; Marcinkowska-Mituś, Agata; Łoboda, Magdalena

    2016-01-01

    Summary The ability to assess bone age accurately is important and allows to diagnose the patient correctly and to plan orthodontic treatment appropriately. The aim of the work is to present views of different authors on the subject of using cephalometric images to determine bone age and its significance for conducting appropriate orthodontic treatment. Publications from the PubMed medical database were analyzed. Search criteria: bone age assessment, CVM method. Ultimately, 36 papers out of 1354 publications were selected. The research of many authors confirms the usefulness of various methods using cephalometric images to assess skeletal age. Currently, the CVM method devised by Baccetti et al. is the most frequently mentioned one in literature. It seems that bone age assessment methods based on evaluating the morphological structure of the cervical vertebrae in cephalometric images can clearly differentiate skeletal maturity in children regardless of their race or sex. Bearing in mind the constant technological progress in medicine and stomatology, bone age assessment methods need to be perfected in order to alleviate their impact on the patient as much as possible. PMID:27536337

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

    International Nuclear Information System (INIS)

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

    1978-05-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-02-01

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

  13. 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.

  14. NecroQuant: quantitative assessment of radiological necrosis

    Science.gov (United States)

    Hwang, Darryl H.; Mohamed, Passant; Varghese, Bino A.; Cen, Steven Y.; Duddalwar, Vinay

    2017-11-01

    Clinicians can now objectively quantify tumor necrosis by Hounsfield units and enhancement characteristics from multiphase contrast enhanced CT imaging. NecroQuant has been designed to work as part of a radiomics pipelines. The software is a departure from the conventional qualitative assessment of tumor necrosis, as it provides the user (radiologists and researchers) a simple interface to precisely and interactively define and measure necrosis in contrast-enhanced CT images. Although, the software is tested here on renal masses, it can be re-configured to assess tumor necrosis across variety of tumors from different body sites, providing a generalized, open, portable, and extensible quantitative analysis platform that is widely applicable across cancer types to quantify tumor necrosis.

  15. Radiological hazard assessment of extracorporeal shock wave lithotripsy devices

    International Nuclear Information System (INIS)

    Sprague, D.D.; Vermeere, W.R.

    1987-01-01

    With the recent introduction of ESWL to the clinical environment, a new health physics challenge has entered the medical consulting area. The x-ray imaging systems used in the devices are of a conventional design, but in an unusual configuration that is difficult to properly assess. The scope of this paper considers specific evaluation problems, and deals with methods developed during experience with 4 units in California. Pertinent regulations are also covered, along with a synopsis of data obtained and ALARA recommendations

  16. 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.

  17. 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

  18. Quality assurance in diagnostic radiology - assessing the fluoroscopic image quality

    International Nuclear Information System (INIS)

    Tabakov, S.

    1995-01-01

    The X-ray fluoroscopic image has a considerably lower resolution than the radiographic one. This requires a careful quality control aiming at optimal use of the fluoroscopic equipment. The basic procedures for image quality assessment of Image Intensifier/TV image are described. Test objects from Leeds University (UK) are used as prototypes. The results from examining 50 various fluoroscopic devices are shown. Their limiting spatial resolution varies between 0.8 lp/mm (at maximum II field size) and 2.24 lp/mm (at minimum field size). The mean value of the limiting spatial resolution for a 23 cm Image Intensifier is about 1.24 lp/mm. The mean limits of variation of the contrast/detail diagram for various fluoroscopic equipment are graphically expressed. 14 refs., 1 fig. (author)

  19. A prospective radiological risk assessment for a phosphate industry project

    Energy Technology Data Exchange (ETDEWEB)

    Lauria, Dejanira C.; Reis, Rocio G., E-mail: dejanira@ird.gov.br, E-mail: rocio@ird.gov.br

    2012-07-01

    The Santa Quiteria Project is the major Brazilian uranium mine project, nowadays. A peculiarity of this project is the association of uranium with phosphate and the mining and processing of both by two different enterprises. A private company will be responsible for the production of phosphoric acid and a state owned company will be responsible for the production of yellow cake. At full capacity, the facility will generate 10% of Brazil's total annual phosphoric acid production and 1,500 tons of yellow cake per year. The processing by which phosphoric acid is produced generates phosphogypsum (PG) as a by-product. The ratio of phosphogypsum to phosphoric acid is around 5 to 1. After all the phosphate has been extracted and processed, it is expected that some 37 million tons of phosphogypsum with 13 Bq/g of {sup 226}Ra will be produced. A prospective generic assessment was carried out for evaluating the potential radioactive impact of this PG stack on the workers and surrounding inhabitants. Two hypothetical farmer scenarios were designed to estimate the potential dose out of the project boundary and over the stack piles, after the shutdown of the project. The annual exposure dose of workers was also evaluated. As a result, the potential public and worker doses exceeded the adopted level of doses of 1mSv.y{sup -1} and 6 mSv.y{sup -1}, respectively. The simulation spotlighted the importance of the rainfall erosion index, and consequently the stack shape for the environmental contamination. The importance of planning the decommissioning of the facility still in the planning phase of the project to give support for the feasibility studies was also highlighter. Although quite conservative, the prospective assessing of dose herein is useful to aware and guide the decision makers on information and data survey and taking avoiding action to protect the health, by changing the project in some way. (author)

  20. Monitoring techniques for the impact assessment during nuclear and radiological emergencies: current status and the challenges

    International Nuclear Information System (INIS)

    Pradeepkumar, K.S.; Sharma, D.N.

    2003-01-01

    Preparedness and response capability for Nuclear and Radiological emergencies, existing world over, are mainly based on the requirement of responding to radiation emergency caused by nuclear or radiological accidents. Cosmos satellite accident, plutonium contamination at Polaris, nuclear accidents like Kystium, Windscale, TMI and Chernobyl, radiological accidents at Goiania etc have demonstrated the requirement of improved radiation monitoring techniques. For quick decision making, state of the art monitoring methodology which can support quantitative and qualitative impact assessment is essential. Evaluation of radiological mapping of the area suspected to be contaminated needs ground based as well as aerial based monitoring systems to predict the level of radioactive contamination on ground. This will help in delineating the area and deciding the required countermeasures, based on the quantity and type of radionuclides responsible for it. The response can be successful with the effective use of i) Early Warning System ii) Mobile Monitoring System and iii) Aerial Gamma Spectrometric System. Selection of the monitoring methodology and survey parameters and assessment of situation using available resources etc. are to be optimized depending on the accident scenario. Recently, many countries and agencies like IAEA have expressed the requirement for responding to other types of nuclear/radiological emergencies i.e, man made radiation emergency situations aimed at harming public at large that can also lead to environmental contamination and significant exposure to public. Reports of lost / misplaced / stolen radioactive sources from many countries are alarming as safety and security of these radioactive sources are under challenge. The monitoring methodology has to take into account of the increase in such demands and more periodic monitoring in suspected locations is to be carried out. Detection of orphan sources possible amidst large heap of metallic scraps may pose

  1. 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

  2. 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

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

    International Nuclear Information System (INIS)

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

    1975-01-01

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

  4. 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

  5. Which radiological investigations should be performed to identify fractures in suspected child abuse?

    International Nuclear Information System (INIS)

    Kemp, A.M.; Butler, A.; Morris, S.; Mann, M.; Kemp, K.W.; Rolfe, K.; Sibert, J.R.; Maguire, S.

    2006-01-01

    Aims: To determine which radiological investigations should be performed and which children should be investigated. Materials and methods: An all language literature search of original articles; from 1950-October 2005. Two reviewers independently reviewed each article. A third was carried out on disagreement. Each study was assessed using standardised data extraction, critical appraisal and evidence forms. Results: Thirty-four studies were included. Fifteen addressed the question: which investigation has a higher yield, skeletal surveys (SS) or bone scintigraphy (BS)? Studies gave conflicting results. Overall neither investigation is as good as the two combined. BS predominately missed skull, metaphyseal and epiphyseal fractures, whereas SS commonly missed rib fractures. Two studies showed that a repeat SS 2 weeks after the initial study provided significant additional information about tentative findings, the number and age of fractures. A comparative study evaluated additional oblique views of ribs in 73 children and showed improved diagnostic sensitivity, specificity and accuracy. Four studies addressed the diagnostic yield for occult fractures with respect to age. This was significant for children under 2-years old. Conclusions: In children under 2-years old, where physical abuse is suspected, diagnostic imaging of the skeleton should be mandatory. SS or BS alone is inadequate to identify all fractures. It is recommended that all SS should include oblique views of the ribs. This review suggests that the following options would optimize the diagnostic yield. However, each needs to be evaluated prospectively: SS that includes oblique views, SS and BS, a SS with repeat SS or selected images 2 weeks later or a BS plus skull radiography and coned views of metaphyses and epiphyses

  6. Which radiological investigations should be performed to identify fractures in suspected child abuse?

    Energy Technology Data Exchange (ETDEWEB)

    Kemp, A.M.; Butler, A.; Morris, S.; Mann, M.; Kemp, K.W.; Rolfe, K.; Sibert, J.R.; Maguire, S

    2006-09-15

    Aims: To determine which radiological investigations should be performed and which children should be investigated. Materials and methods: An all language literature search of original articles; from 1950-October 2005. Two reviewers independently reviewed each article. A third was carried out on disagreement. Each study was assessed using standardised data extraction, critical appraisal and evidence forms. Results: Thirty-four studies were included. Fifteen addressed the question: which investigation has a higher yield, skeletal surveys (SS) or bone scintigraphy (BS)? Studies gave conflicting results. Overall neither investigation is as good as the two combined. BS predominately missed skull, metaphyseal and epiphyseal fractures, whereas SS commonly missed rib fractures. Two studies showed that a repeat SS 2 weeks after the initial study provided significant additional information about tentative findings, the number and age of fractures. A comparative study evaluated additional oblique views of ribs in 73 children and showed improved diagnostic sensitivity, specificity and accuracy. Four studies addressed the diagnostic yield for occult fractures with respect to age. This was significant for children under 2-years old. Conclusions: In children under 2-years old, where physical abuse is suspected, diagnostic imaging of the skeleton should be mandatory. SS or BS alone is inadequate to identify all fractures. It is recommended that all SS should include oblique views of the ribs. This review suggests that the following options would optimize the diagnostic yield. However, each needs to be evaluated prospectively: SS that includes oblique views, SS and BS, a SS with repeat SS or selected images 2 weeks later or a BS plus skull radiography and coned views of metaphyses and epiphyses.

  7. Assessment of natural radioactivity and associated radiological risks from tiles used in Kajang, Malaysia

    Science.gov (United States)

    Abdullahi, S.; Ismail, A. F.; Samat, S. B.; Yasir, M. S.

    2018-04-01

    The activity concentration and radiological risk of commonly used flooring materials (tiles) in Malaysia were studied. The natural radionuclide concentrations of 226Ra, 232Th and 40K were measured using high-purity germanium detector. The average concentration of 226Ra, 232Th and 40K in the samples were 65.75±1.1 Bq kg-1, 61.92±1.43 Bq kg-1 and 617.77±6.72 Bq kg-1 respectively. The mean concentration of radium equivalent activity, absorbed dose rate, external and internal hazard indices and annual effective dose equivalent were 195.21±2.88 Bq kg-1, 92.75±1.27 nGy h-1, 0.53±0.01, 0.7±0.01 and 0.44±0.0 mSv y-1 respectively. The aim was to assess the possible radiological risks attributed from the tile materials. Even though, the activity concentrations were higher than worldwide average values, but none of the radiological impact parameters exceeded the maximum recommended values. Hence, it was concluded that, contribution of tiles to radiation exposure is negligible and therefore, radiologically safe to use as building materials.

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

    Science.gov (United States)

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

    2016-04-01

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

  9. Soil-to-plant concentration factors for radiological assessments

    International Nuclear Information System (INIS)

    Ng, Y.C.; Thompson, S.E.; Colsher, C.S.

    1982-09-01

    This report presents the results of a literature review to derive soil-to-plant concentration factors to predict the concentration of a radionuclide in plants from that in soil. The concentration factor, B/sub v/ is defined as the ratio of the concentration of a nuclide in the edible plant part to that in dry soil. CR (the concentration ratio) is similarly defined to denote the concentration factor for dry feed consumed by livestock. B/sub v/ and CR values are used to assess the dose from radionuclides deposited onto soil and transferred into crop plants via roots. Approaches for deriving B/sub v/ and CR values are described, and values for food and feed are tabulated for individual elements. The sources of uncertainty are described, and the factors that contribute to the inherent variability of the B/sub v/ and CR values are discussed. Summary tables of elemental B/sub v/ and CR values and statistical parameters that characterize their distributions provide a basis for a systematic updating of many of the B/sub v/ values in Regulatory Guide 1.109. They also provide a basis for selecting B/sub v/ and CR values for other applications that involve the use of equilibrium models to predict the concentration of radionuclides in plants from that in soil

  10. Radiologic assessment in the pediatric intensive care unit

    International Nuclear Information System (INIS)

    Markowitz, R.I.

    1984-01-01

    The severely ill infant or child who requires admission to a pediatric intensive care unit (PICU) often presents with a complex set of problems necessitating multiple and frequent management decisions. Diagnostic imaging plays an important role, not only in the initial assessment of the patient's condition and establishing a diagnosis, but also in monitoring the patient's progress and the effects of interventional therapeutic measures. Bedside studies obtained using portable equipment are often limited but can provide much useful information when a careful and detailed approach is utilized in producing the radiograph and interpreting the examination. This article reviews some of the basic principles of radiographic interpretation and details some of the diagnostic points which, when promptly recognized, can lead to a better understanding of the patient's condition and thus to improved patient care and management. While chest radiography is stressed, studies of other regions including the upper airway, abdomen, skull, and extremities are discussed. A brief consideration of the expanding role of new modality imaging (i.e., ultrasound, CT) is also included. Multiple illustrative examples of common and uncommon problems are shown

  11. Inner ear anatomy in Waardenburg syndrome: radiological assessment and comparison with normative data.

    Science.gov (United States)

    Kontorinis, Georgios; Goetz, Friedrich; Lanfermann, Heinrich; Luytenski, Stefan; Giesemann, Anja M

    2014-08-01

    As patients with Waardenburg syndrome (WS) represent potential candidates for cochlear implantation, their inner ear anatomy is of high significance. There is an ongoing debate whether WS is related to any inner ear dysplasias. Our objective was to evaluate radiologically the inner ear anatomy in patients with WS and identify any temporal bone malformations. A retrospective case review was carried out in a tertiary, referral center. The high resolution computed tomography (HRCT) scans of the temporal bone from 20 patients (40 ears) with WS who were managed for deafness in a tertiary referral center from 1995 to 2012 were retrospectively examined. Measurements of 15 different inner ear dimensions, involving the cochlea, the vestibule, the semicircular canals and the internal auditory meatus, as well as measurements of the vestibular aqueduct, were performed independently by two neuroradiologists. Finally, we compared the results from the WS group with a control group consisting of 50 normal hearing subjects (100 ears) and with previously reported normative values. Inner ear malformations were not found in any of the patients with WS. All measured inner ear dimensions were within the normative values compiled by our study group as well as by others. Inner ear malformations are not characteristic for all types of WS; however, certain rare subtypes might be related to inner ear deformities. Normative cochleovestibular dimensions that can help in assessing the temporal bone anatomy are provided. Copyright © 2014 Elsevier Ireland Ltd. All rights reserved.

  12. Feasibility of disposal of high-level radioactive waste into the seabed. Volume 2: Radiological assessment

    International Nuclear Information System (INIS)

    Marsily, G. de; Berhendt, V.; Ensminger, D.; Flebus, C.; Hutchinson, B.; Kane, P.; Karpf, A.; Klett, R.; Mobbs, S.; Poulin, M.; Stanner, D.

    1988-01-01

    One of the options suggested for disposal of high-level radioactive waste resulting from the generation of nuclear power is burial beneath the deep ocean floor in geologically stable sediment formations which have no economic value. The 8-volume series provides an assessment of the technical feasibility and radiological safety of this disposal concept based on the results obtained by ten years of co-operation and information exchange among the Member countries participating in the NEA Seabed Working Group. This report presents the results of the radiological assessment which consists in estimating the detriment to man and to the environment which could result from the disposal of high level nuclear waste within seabed sediments in the deep oceans

  13. 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

  14. Evaluation of Radiology Teachers' Performance and Identification of the "Best Teachers" in a Residency Program: Mixed Methodology and Pilot Study of the MEDUC-RX32 Questionnaire.

    Science.gov (United States)

    Huete, Álvaro; Julio, Rodrigo; Rojas, Viviana; Herrera, Cristián; Padilla, Oslando; Solís, Nancy; Pizarro, Margarita; Etcheberry, Lorena; Sarfatis, Alberto; Pérez, Gonzalo; Díaz, Luis A; Delfino, Alejandro; Muñoz, Estrella; Rivera, Horacio; Parra, Dimitri A; Bitran, Marcela; Riquelme, Arnoldo

    2016-07-01

    Radiology teachers are well trained in their specialty; however, when working in academic institutions, faculty development and promotion through the education pathway tends to be based on their teaching knowledge and skills. The aim of this study is to assess psychometric properties of the Medicina Universidad Católica-Radiology 32 items (MEDUC-RX32), an instrument designed to evaluate the performance of postgraduate radiology teachers and to identify the best teachers. Mixed methodology was used, including qualitative and quantitative phases. The psychometric properties of the MEDUC-RX32 survey were performed by factor analysis (validity), Cronbach alpha coefficient, and G coefficient (reliability). The residents assessed their teachers and simultaneously voted for the "best teacher," which was used as a gold standard for the receiver operating characteristic curves construction comparing their votes with the global score. A total of 28 residents answered 164 surveys. The global score was 6.23 ± 0.8 (scale from 1 to 7). The factor analysis showed six domains of the resident's perception: (1) tutorial teaching, feedback, and independent learning; (2) communication and teamwork; (3) learning objectives; (4) respectful behavior; (5) radiological report; and (6) teaching and care support. The tutor's strengths were related with respectful behavior and teamwork. The instrument is highly reliable with a Cronbach alpha of 0.937 and a G coefficient of 0.831 (with a minimum of 8 residents). The MEDUC-RX32 instrument has a sensitivity of 91.7% and specificity of 83.3% to identify tutors as best teachers with at least one vote with an area under the receiver operating characteristic curve of 0.931 with a cutoff of 5.94. The MEDC-RX32 instrument is a multidimensional, valid, and highly reliable method to evaluate radiology teachers, identifying teachers with excellence in tutorial teaching in a postgraduate radiology program. Copyright © 2016 The Association of

  15. Radiologic Assessment of Native Renal Vasculature: A Multimodality Review.

    Science.gov (United States)

    Al-Katib, Sayf; Shetty, Monisha; Jafri, Syed Mohammad A; Jafri, Syed Zafar H

    2017-01-01

    A wide range of clinically important anatomic variants and pathologic conditions may affect the renal vasculature, and radiologists have a pivotal role in the diagnosis and management of these processes. Because many of these entities may not be suspected clinically, renal artery and vein assessment is an essential application of all imaging modalities. An understanding of the normal vascular anatomy is essential for recognizing clinically important anatomic variants. An understanding of the protocols used to optimize imaging modalities also is necessary. Renal artery stenosis is the most common cause of secondary hypertension and is diagnosed by using both direct ultrasonographic (US) findings at the site of stenosis and indirect US findings distal to the stenosis. Fibromuscular dysplasia, while not as common as atherosclerosis, remains an important cause of renal artery hypertension, especially among young female individuals. Fibromuscular dysplasia also predisposes individuals to renal artery aneurysms and dissection. Although most renal artery dissections are extensions of aortic dissections, on rare occasion they occur in isolation. Renal artery aneurysms often are not suspected clinically before imaging, but they can lead to catastrophic outcomes if they are overlooked. Unlike true aneurysms, pseudoaneurysms are typically iatrogenic or posttraumatic. However, multiple small pseudoaneurysms may be seen with underlying vasculitis. Arteriovenous fistulas also are commonly iatrogenic, whereas arteriovenous malformations are developmental (ie, congenital). Both of these conditions involve a prominent feeding artery and draining vein; however, arteriovenous malformations contain a nidus of tangled vessels. Nutcracker syndrome should be suspected when there is distention of the left renal vein with abrupt narrowing as it passes posterior to the superior mesenteric artery. Filling defects in a renal vein can be due to a bland or tumor thrombus. A tumor thrombus is

  16. Radiological hazard assessment at the Monte Bello Islands

    International Nuclear Information System (INIS)

    Cooper, M.B.; Martin, L.J.; Wilks, M.J.; Wiliams, G.A.

    1990-12-01

    Field and laboratory measurements are described and data presented which enabled dose assessments for exposure to artificial radionuclides at the Monte Bello Islands, the sites of U.K. atomic weapons tests in 1952 and 1956. The report focuses on quantifying the inhalation hazard as exposure via the ingestion and wound contamination pathways is considered inconsequential. Surface soil concentrations of radionuclides and particle size analyses are presented for various sampling sites. Analyses of the distribution with depth indicated that, in general, the activity is more or less uniformly mixed through the top 40 mm, although in a few cases the top 10 mm contains the bulk of the activity. The 239 Pu/ 241 Am activity ratios were measured for selected samples. The only potential hazards to health from residual radioactive contamination on the Monte Bello Islands are due to the inhalation of actinides (specifically plutonium and americium) and from the external gamma-radiation field. Only one area, in the fallout plume of HURRICANE to the north-west of Main Beach, is a potential inhalation hazard. For an average inhalable dust loading of 0.1 mg/m 3 , three days occupancy of the most contaminated site will result in a committed effective dose equivalent of 1 mSv. The two ground zeros could not be considered inhalation hazards, considering the small areas concerned and the habits of visitors (full-time occupancy, over a period of one year or more, of the most contaminated sites at either of the G1 or G2 ground zeros would be required to reach 1 mSv). 25 refs., 23 tabs., 3 figs

  17. Assessment of the radiological impact of selected building materials

    International Nuclear Information System (INIS)

    Gwiazdowski, B.

    1983-02-01

    Naturally occurring radionuclides in building materials are a source of external and internal radiation exposure to essentially the entire Polish population. The programme of our studies met two main aspects on radioactivity of building materials: Gamma dose rate and radon or alpha potential energy concentration measurements in dwellings of various kinds of structure and materials in both industrial and rural districts of Poland. Gamma dose rate measurements were made in about 2200 dwellings and radon or alpha potential energy concentration measurements - in 750 dwellings. On the basis of these studies the annual effective dose equivalent to the Polish population due to gamma and alpha radiation indoors was estimated to be 0.39 mSv/a and 0.99 mSv/a, respectively. The contribution of external (from gamma) and internal (from alpha) radiation exposure due to naturally occurring radionuclides in building materials to the total radiation exposure of Polish population was assessed to be 3.6 per cent and 34.2 per cent, respectively. Measurements of about 1500 samples of various kinds of building materials and raw materials were made to determine radionuclide concentrations in them. The highest values were obtained in samples of phosphogypsum, fly ash and slag: potassium concentration ranges up to 36 pCi g -1 (a slag sample), radium - up to 17 pCi g -1 (a phosphogypsum sample) and thorium - up to 4 pCi g -1 (a phosphogypsum). On the basis of the results of our studies we came to the conclusion that it was necessary to work out a control system which could protect habitants against enhancement of indoor exposure to ionizing radiation

  18. 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)

  19. Analysis and radiological assessment of survey results and samples from the beaches around Sellafield

    International Nuclear Information System (INIS)

    Webb, G.A.M.; Fry, F.A.

    1983-12-01

    After radioactive sea debris had been found on beaches near the BNFL, Sellafield, plant, NRPB was asked by the Department of the Environment to analyse some of the samples collected and to assess the radiological hazard to members of the public. A report is presented containing an analysis of survey reports for the period 19 November - 4 December 1983 and preliminary results of the analysis of all samples received, together with the Board's recommendations. (author)

  20. Comparison of Performance Characteristics of American College of Radiology TI-RADS, Korean Society of Thyroid Radiology TIRADS, and American Thyroid Association Guidelines.

    Science.gov (United States)

    Middleton, William D; Teefey, Sharlene A; Reading, Carl C; Langer, Jill E; Beland, Michael D; Szabunio, Margaret M; Desser, Terry S

    2018-05-01

    The American College of Radiology (ACR) Thyroid Imaging Reporting and Data System (TI-RADS) provides guidelines to practitioners who interpret sonographic examinations of thyroid nodules. The purpose of this study is to compare the ACR TI-RADS system with two other well-established guidelines. The ACR TI-RADS, the Korean Society of Thyroid Radiology (KSThR) Thyroid Imaging Reporting and Data System (TIRADS), and the American Thyroid Association guidelines were compared using 3422 thyroid nodules for which pathologic findings were available. The composition, echogenicity, margins, echogenic foci, and size of the nodules were assessed to determine whether a recommendation would be made for fine-needle aspiration or follow-up sonography when each system was used. The biopsy yield of malignant findings, the yield of follow-up, and the percentage of malignant and benign nodules that would be biopsied were determined for all nodules and for nodules 1 cm or larger. The percentage of nodules that could not be classified was 0%, 3.9%, and 13.9% for the ACR TI-RADS, KSThR TIRADS, and ATA guidelines, respectively. The biopsy yield of malignancy was 14.2%, 10.2%, and 10.0% for nodules assessed by the ACR TI-RADS, KSThR TIRADS, and ATA guidelines, respectively. The percentage of malignant nodules that were biopsied was 68.2%, 78.7%, and 75.9% for the ACR TI-RADS, the KSThR TIRADS, and the ATA guidelines, respectively, whereas the percentage of malignant nodules that would be either biopsied or followed was 89.2% for the ACR TI-RADS. The percentage of benign nodules that would be biopsied was 47.1%, 79.7%, and 78.1% for the ACR TI-RADS, the KSThR TIRADS, and the ATA guidelines, respectively. The percentage of benign nodules that would be either biopsied or followed was 65.2% for the ACR TI-RADS. The ACR TI-RADS performs well when compared with other well-established guidelines.

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

    International Nuclear Information System (INIS)

    Mohd Khalid Matori; Husaini Salleh; Muhammad Jamal Muhammad Isa

    2014-01-01

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

  2. Radiological assessment of the femoral bowing in Japanese population

    Directory of Open Access Journals (Sweden)

    Abdelaal Ahmed Hamed Kassem

    2016-01-01

    Full Text Available Introduction: Differences in the magnitude of bowing between races are well-known characteristics of the femur. Asian races have an increased magnitude of femoral bowing but most of the orthopedic implants designed for the femur do not match this exaggerated bowing. We calculated the sagittal and coronal femoral bowing in the Japanese population at different levels of the femur and addressed its surgical significance. Material and methods: We calculated the sagittal and coronal bowing of 132 Japanese femora using CT scan of the femur. A mathematical calculation of the radius of curvature at proximal, middle, and distal regions of the femur was used to determine the degree of femoral bowing. Results: Mean sagittal bowing of the femur was 581, 188, and 161 mm for the proximal, middle, and distal thirds of the femur and mean lateral bowing was 528, 5092, and 876 mm, respectively. Mean sagittal and coronal bowing for the whole femur was 175 and 2640 mm, respectively. No correlation was found between age, gender, length of femur, and the degree of bowing. Conclusion: Our study reveals that femoral bowing in the Japanese population is 175 mm in the sagittal plane and 2640 mm in the coronal plane; these values are greater than the femoral bowing in other ethnic groups studied in the literature. This may result in varying degrees of mismatch between the western-manufactured femoral intramedullary implants and the Japanese femur. We recommend that orthopedic surgeons to accurately perform preoperative evaluation of the femoral bowing to avoid potential malalignment, rotation, and abnormal stresses between the femur and implant.

  3. Radiologic assessment of maxillofacial, mandibular, and skull base trauma

    International Nuclear Information System (INIS)

    Schuknecht, Bernhard; Graetz, Klaus

    2005-01-01

    Cranio-maxillofacial injuries affect a significant proportion of trauma patients either in isolation or concurring with other serious injuries. Contrary to maxillofacial injuries that result from a direct impact, central skull base and lateral skull base (petrous bone) fractures usually are caused by a lateral or sagittal directed force to the skull and therefore are indirect fractures. The traditional strong role of conventional images in patients with isolated trauma to the viscerocranium is decreasing. Spiral multislice CT is progressively replacing the panoramic radiograph, Waters view, and axial films for maxillofacial trauma, and is increasingly being performed in addition to conventional films to detail and classify trauma to the mandible as well. Imaging thus contributes to accurately categorizing mandibular fractures based on location, into alveolar, mandibular proper, and condylar fractures - the last are subdivided into intracapsular and extracapsular fractures. In the midface, CT facilitates attribution of trauma to the categories central, lateral, or combined centrolateral fractures. The last frequently encompass orbital trauma as well. CT is the imaging technique of choice to display the multiplicity of fragments, the degree of dislocation and rotation, or skull base involvement. Transsphenoid skull base fractures are classified into transverse and oblique types; lateral base (temporal bone) trauma is subdivided into longitudinal and transverse fractures. Supplementary MR examinations are required when a cranial nerve palsy occurs in order to recognize neural compression. Early and late complications of trauma related to the orbit, anterior cranial fossa, or lateral skull base due to infection, brain concussion, or herniation require CT to visualize the osseous prerequisites of complications, and MR to define the adjacent brain and soft tissue involvement. (orig.)

  4. Sequestration Coating Performance Requirements for Mitigation of Contamination from a Radiological Dispersion Device

    International Nuclear Information System (INIS)

    Drake, J.

    2009-01-01

    Immediate action would be necessary to minimize the effects of a radiological 'dirty bomb' detonation in a major city. After a dirty bomb has been detonated, vehicular and pedestrian traffic, as well as weather effects, would increase the spread of loose contamination, making control and recovery more difficult and costly. While contaminant migration and chemical binding into surface materials can be relatively rapid, the immediate treatment of surfaces with large quantities of an appropriate compound could alleviate much of the difficulty in decontamination. The EPA's National Homeland Security Research Center (NHSRC), in collaboration with ASTM International, is currently developing performance standards for materials which could be applied to exterior surfaces contaminated by an RDD to mitigate the spread and migration of radioactive contamination. These performance standards are being promulgated via an ASTM Standard Specification to be published by ASTM International. Test methods will be developed to determine if candidate coatings meet the performance requirements stipulated in the ASTM performance standard. These test methods will be adapted from existing standard methods, or will be devised through laboratory research. The final set of test methods will be codified in an ASTM or other standard test method. The principal market for products described in the ASTM performance standard would be federal, state and local government emergency responders and response planners, decontamination service providers and those whose interests include protection and recovery of real estate potentially at risk from radiological terrorism. (authors)

  5. Radiological assessment of depleted uranium impact locations in Iraq

    International Nuclear Information System (INIS)

    Smith, D.; Brown, R.

    2006-01-01

    Although the monitoring that could be carried out during this brief reconnaissance was neither entirely systematic nor completely representative of overall environmental conditions, it is interesting to compare the activity concentrations of D.U. (depleted uranium) found in this work with what would be considered benchmark quantities. This has been done in some of the following sections, but it must be recognised that the data is not of the quality needed for robust generalised statements about D.U. contamination or any possible health consequences. D.U. mainly consists of 238 U, 235 U and 234 U. All of these isotopes have different radioactive decay characteristics and therefore different dose per unit intake factors. However, for dose assessment purposes, it can easily be shown that the assumption that D.U. is composed entirely of 238 U will result in an insignificant error in estimating the likely magnitude of any radiation dose. For example, for the limiting (i.e. highest) dose per unit intake factors given in ICRP 72 [2] for each isotope, this assumption gives rise to differences of about 1% and 10% for inhalation and ingestion respectively. This approximation has been used in the following discussions. 7.2 General observations Four D.U. contaminated tanks and one anti-aircraft gun were located and surveyed during the reconnaissance, together with two areas of contaminated land. There were also visual indications of D.U. impacts on two other tanks and an armored personnel carrier, but time constraints and hazards from unstable structures and unexploded ordnance prevented investigation of these vehicles. The most surprising finding was that there was relatively little loose contamination on or in the tanks. A more detailed interpretation of the results follows. 7.3 Smear samples All smears were subject to α and β counting and the results of the α counting converted to an equivalent removable surface contamination level, expressed in terms of Bq cm -2 , by

  6. Radiological assessment of depleted uranium impact locations in Iraq

    Energy Technology Data Exchange (ETDEWEB)

    Smith, D.; Brown, R. [Dstl Environmental Sciences Dept., Crescent Road, Alverstoke, Gosport, Hants PO12 2DL (United Kingdom)

    2006-07-01

    Although the monitoring that could be carried out during this brief reconnaissance was neither entirely systematic nor completely representative of overall environmental conditions, it is interesting to compare the activity concentrations of D.U. (depleted uranium) found in this work with what would be considered benchmark quantities. This has been done in some of the following sections, but it must be recognised that the data is not of the quality needed for robust generalised statements about D.U. contamination or any possible health consequences. D.U. mainly consists of {sup 238}U, {sup 235}U and {sup 234}U. All of these isotopes have different radioactive decay characteristics and therefore different dose per unit intake factors. However, for dose assessment purposes, it can easily be shown that the assumption that D.U. is composed entirely of {sup 238}U will result in an insignificant error in estimating the likely magnitude of any radiation dose. For example, for the limiting (i.e. highest) dose per unit intake factors given in ICRP 72 [2] for each isotope, this assumption gives rise to differences of about 1% and 10% for inhalation and ingestion respectively. This approximation has been used in the following discussions. 7.2 General observations Four D.U. contaminated tanks and one anti-aircraft gun were located and surveyed during the reconnaissance, together with two areas of contaminated land. There were also visual indications of D.U. impacts on two other tanks and an armored personnel carrier, but time constraints and hazards from unstable structures and unexploded ordnance prevented investigation of these vehicles. The most surprising finding was that there was relatively little loose contamination on or in the tanks. A more detailed interpretation of the results follows. 7.3 Smear samples All smears were subject to {alpha} and {beta} counting and the results of the {alpha} counting converted to an equivalent removable surface contamination level

  7. Radiological risk assessment for an urban area: Focusing on a drinking water contamination

    International Nuclear Information System (INIS)

    Jeong, Hyo-Joon; Hwang, Won-Tae; Kim, Eun-Han; Han, Moon-Hee

    2009-01-01

    This paper specifically discusses a water quality modeling and health risk assessment for cesium-137 to assess the potential and actual effects on human health from drinking water contaminated by a radiological terrorist attack in the Seoul metropolitan area, Korea. With respect to the source term caused by a terrorist attack, it was assumed that 50 TBq of cesium-137 was introduced into the Paldang Lake which is a single water resource for the Seoul metropolitan area. EFDC (Environmental Fluid Dynamics Code) model was used to calculate the hydrodynamic and water quality for the model domain, Paldang Lake. Mortality risk and morbid risk coefficients caused by the ingestion of tap water were used to assess a human health risk due to cesium-137. The transport of cesium-137 in the Paldang water system was mainly dependent on the flow streamlines and the effect of the dilution from the other branches. The mortality and morbidity risks due to the drinking water contamination by cesium-137 were 4.77 x 10 -7 and 6.92 x 10 -7 , respectively. Accordingly, it is very important to take appropriate countermeasures when radiological terrorist attacks have occurred at water resources to prevent radiological risks by radionuclides.

  8. A Poor Man's Nuclear Deterrent: Assessing the Value of Radiological Weapons for State Actors

    Science.gov (United States)

    Donohue, Nathan

    , "Radiological Dispersal Devices: Assessing the Transnational Threat," Strategic Forum, No. 136, (March 1998), March 29, 2012, http://www.au.af.mil/au/awc/awcgate/ndu/forum136.htm.

  9. Performance assessment: a peer review

    International Nuclear Information System (INIS)

    Lieberman, J.A.; Lee, W.W.L.

    1986-01-01

    This paper describes the rationale, membership, operation and major observations of the Performance Assessment National Review Group. The Group was assembled by Weston at the request of the US Department of Energy Office of Civilian Radioactive Waste Management to review performance assessment work in the US basalt, salt and tuff repository projects. The purposes were to evaluate the adequacy of the current methods, identify deficiencies, and suggest potential improvement on repository performance assessment. To perform the review, Weston retained a group of distinguished consultants who have had extensive experience in disciplines pertinent to management of radioactive wastes including mathematical modeling of fluid transport. Topics reviewed included flow and transport, source term and uncertainty analysis. While the emphasis was on methodologies, the Projects were specifically requested to show currently available results so that the way they utilized familiar methodologies could be evaluated. This paper will highlight some of the technical observations of the Group as well as some managerial and institutional issues

  10. Assessment of the radiological conditions in areas of Kuwait with residues of depleted uranium

    International Nuclear Information System (INIS)

    Cabianca, T.; Danesi, P.R.; Linsley, G.

    2004-01-01

    The 1991 Gulf War was the first conflict in which DU munitions were used extensively. After this conflict, questions arose regarding the possible link between exposure to ionizing radiation from DU and harmful biological effects. In view of these concerns, the Government of Kuwait, in February 2001, requested the IAEA to conduct an assessment to evaluate the possible radiological impact of residues of DU munitions from the 1991 Gulf War at 11 locations in Kuwait. For this purpose, the IAEA assembled a team of senior experts, who visited Kuwait in September 2001 to carry out a preliminary assessment of the sites and to evaluate the available information. In February 2002 scientists from the IAEA, the Spiez Laboratory (Switzerland), representing UNEP, and the Radiation Protection Department of the Ministry of Health of Kuwait, carried out a sampling campaign at these sites. Around 200 environmental samples, including soil, water and vegetation, were collected during the campaign and subsequently analysed. This study constitutes the first comprehensive radiological assessment of compliance with international radiation protection criteria and standards for areas with residues of DU munitions conducted under the auspices of the IAEA. The findings of this investigation indicate that DU does not pose a radiological hazard to the population of Kuwait. Annual radiation doses arising from exposure to DU residues would be of a few micro-sieverts, well below the annual doses from natural sources of radiation and far below the reference level recommended by the IAEA as a criterion to help establish whether remedial actions are necessary. DU penetrators can still be found at some of the locations visited. Prolonged skin contact with these residues is the only possible pathway that could result in exposures of radiological significance. As long as access to these areas remains restricted, the likelihood that members of the public could come into contact with these residues is low

  11. Direction Committee for the management of the post-accident phase of a nuclear accident or of a radiological event (CODIRPA). Work group 'Hypotheses'. Contextual data and hypotheses to perform predictive assessments of radiological and dose consequences at the beginning of a post-accidental transition phase. 2007-2009 work report

    International Nuclear Information System (INIS)

    2010-01-01

    This report first describes how to examine the various exposure ways of a person present on a contaminated territory and formulates hypotheses for the calculation of radioactive doses received by ingestion of contaminated food products, by external irradiation, or by involuntary inhalation of radioactive particles. It identifies factors which may influence the contamination of food products, and gives recommendations for the predictive calculation of their contamination during the first month following the accident. It indicates available methods for the predictive assessment of radioactive deposits at the beginning of the transition phase. It proposes an expertise method to assess the post-accident consequences

  12. Is radiological evaluation as good as computer-based volumetry to assess hippocampal atrophy in Alzheimer's disease?

    International Nuclear Information System (INIS)

    Boutet, Claire; Drier, Aurelie; Dormont, Didier; Lehericy, Stephane; Chupin, Marie; Colliot, Olivier; Sarazin, Marie; Mutlu, Gurkan; Pellot, Audrey

    2012-01-01

    Hippocampus volumetry is a useful surrogate marker for the diagnosis of Alzheimer's disease (AD). Our purpose was to compare visual assessment of medial temporal lobe atrophy made by radiologists with automatic hippocampal volume and to compare their performances for the classification of AD, mild cognitive impairment (MCI) and cognitively normal (CN). We studied 30 CN, 30 MCI and 30 AD subjects. Six radiologists with two levels of expertise performed two readings of medial temporal lobe atrophy. Medial temporal lobe atrophy was evaluated on coronal three-dimensional T1-weighted images using Scheltens scale and compared with hippocampal volume obtained using a fully automatic segmentation method (Spearman's rank coefficient). Visual assessment of medial temporal lobe atrophy was correlated with hippocampal volume (p < 0.01). Classification performances between MCI converter and CN was better using volumetry than visual assessment of non-expert readers whereas classification of AD and CN did not differ between visual assessment and volumetry except for the first reading of one non-expert (p = 0.03). Visual assessment of medial temporal lobe atrophy by radiologists was well correlated with hippocampal volume. Radiological assessment is as good as computer-based volumetry for the classification of AD, MCI non-converter and CN and less good for the classification of MCI converter versus CN. Use of Scheltens scale for assessing hippocampal atrophy in AD seems thus justified in clinical routine. (orig.)

  13. Is radiological evaluation as good as computer-based volumetry to assess hippocampal atrophy in Alzheimer's disease?

    Energy Technology Data Exchange (ETDEWEB)

    Boutet, Claire; Drier, Aurelie; Dormont, Didier; Lehericy, Stephane [Groupe Hospitalier Pitie-Salpetriere, Department of Neuroradiology, AP-HP, Paris Cedex 13 (France); Universite Pierre et Marie Curie-Paris 6, Centre de Recherche de l' Institut du Cerveau et de la Moelle epiniere, UMR-S975, Paris (France); Inserm, Paris (France); CNRS, Paris (France); ICM-Institut du Cerveau et de la Moelle epiniere, Paris (France); Chupin, Marie; Colliot, Olivier [Universite Pierre et Marie Curie-Paris 6, Centre de Recherche de l' Institut du Cerveau et de la Moelle epiniere, UMR-S975, Paris (France); Inserm, Paris (France); CNRS, Paris (France); ICM-Institut du Cerveau et de la Moelle epiniere, Paris (France); Equipe Cogimage-CRICM, Paris Cedex 13 (France); Sarazin, Marie [Universite Pierre et Marie Curie-Paris 6, Centre de Recherche de l' Institut du Cerveau et de la Moelle epiniere, UMR-S975, Paris (France); Inserm, Paris (France); CNRS, Paris (France); ICM-Institut du Cerveau et de la Moelle epiniere, Paris (France); Groupe Hospitalier Pitie-Salpetriere, Department of Neurology, Institut de la Memoire et de la Maladie d' Alzheimer-IM2A, Paris Cedex 13 (France); Mutlu, Gurkan [Groupe Hospitalier Pitie-Salpetriere, Urgences Cerebro-Vasculaires, Universite Pierre et Marie Curie-Paris 6, Paris Cedex 13 (France); Hopital Saint-Louis, Inserm, Universite Paris 7-Denis Diderot, Paris (France); Pellot, Audrey [Groupe Hospitalier Pitie-Salpetriere, Department of Neuroradiology, AP-HP, Paris Cedex 13 (France); Collaboration: And the Alzheimer' s Disease Neuroimaging Initiative

    2012-12-15

    Hippocampus volumetry is a useful surrogate marker for the diagnosis of Alzheimer's disease (AD). Our purpose was to compare visual assessment of medial temporal lobe atrophy made by radiologists with automatic hippocampal volume and to compare their performances for the classification of AD, mild cognitive impairment (MCI) and cognitively normal (CN). We studied 30 CN, 30 MCI and 30 AD subjects. Six radiologists with two levels of expertise performed two readings of medial temporal lobe atrophy. Medial temporal lobe atrophy was evaluated on coronal three-dimensional T1-weighted images using Scheltens scale and compared with hippocampal volume obtained using a fully automatic segmentation method (Spearman's rank coefficient). Visual assessment of medial temporal lobe atrophy was correlated with hippocampal volume (p < 0.01). Classification performances between MCI converter and CN was better using volumetry than visual assessment of non-expert readers whereas classification of AD and CN did not differ between visual assessment and volumetry except for the first reading of one non-expert (p = 0.03). Visual assessment of medial temporal lobe atrophy by radiologists was well correlated with hippocampal volume. Radiological assessment is as good as computer-based volumetry for the classification of AD, MCI non-converter and CN and less good for the classification of MCI converter versus CN. Use of Scheltens scale for assessing hippocampal atrophy in AD seems thus justified in clinical routine. (orig.)

  14. DOE site performance assessment activities

    International Nuclear Information System (INIS)

    1990-07-01

    Information on performance assessment capabilities and activities was collected from eight DOE sites. All eight sites either currently dispose of low-level radioactive waste (LLW) or plan to dispose of LLW in the near future. A survey questionnaire was developed and sent to key individuals involved in DOE Order 5820.2A performance assessment activities at each site. The sites surveyed included: Hanford Site (Hanford), Idaho National Engineering Laboratory (INEL), Los Alamos National Laboratory (LANL), Nevada Test Site (NTS), Oak Ridge National Laboratory (ORNL), Paducah Gaseous Diffusion Plant (Paducah), Portsmouth Gaseous Diffusion Plant (Portsmouth), and Savannah River Site (SRS). The questionnaire addressed all aspects of the performance assessment process; from waste source term to dose conversion factors. This report presents the information developed from the site questionnaire and provides a comparison of site-specific performance assessment approaches, data needs, and ongoing and planned activities. All sites are engaged in completing the radioactive waste disposal facility performance assessment required by DOE Order 5820.2A. Each site has achieved various degrees of progress and have identified a set of critical needs. Within several areas, however, the sites identified common needs and questions

  15. Selection of nuclide decay chains for use in the assessment of the radiological impact of geological repositories for radioactive waste

    International Nuclear Information System (INIS)

    Thorne, M.C.

    1982-12-01

    The criteria for selecting nuclide decay chains for use in the assessment of the radiological impact of geological repositories for radioactive waste are given. The reduced chains recommended for use with SYVAC are described. (author)

  16. A computerized assessment and response system for radiological emergency at Diablo Canyon Nuclear Power Plant

    International Nuclear Information System (INIS)

    Shih, C.C.; Thuillier, R.H.

    1984-01-01

    The U.S. Nuclear Regulatory Commission requires that nuclear power plants provide for rapid assessment and response in the event of a radiological emergency. At the Diablo Canyon Nuclear Power Plant, Pacific Gas and Electric Company uses a system of linked central minicomputer, satellite desktop computers and microprocessors to provide decision makers with timely and pertinent information in emergency situations. The system provides for data acquisition and microprocessing at meteorological and radiological monitoring sites. Current estimates or projections of offsite dose commitment are made in real-time by a dispersion/dose calculation model. Computerized dissemination of data and calculational results to decision makers at the government and utility levels is also available. The basic system in use is a commercially available Emergency Assessment and Response System (EARS). This generic system has been modified in-house to meet requirements specific to emergency situations at the plant. Distinctive features of the modification program includes: a highly professional man-machine interaction; consideration of site-specific factors; simulation of environmental radiology for development of drill scenarios; and concise, pertinent reports as input to decision making

  17. 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.

  18. Preliminary radiological safety assessment for decommissioning of thoria dissolver of the 233U pilot plant, Trombay

    International Nuclear Information System (INIS)

    Priya, S.; Srinivasan, P.; Gopalakrishnan, R. K.

    2012-01-01

    The thoria dissolver, used for separation of 233 U from reactor-irradiated thorium metal and thorium oxide rods, is no longer operational. It was decided to carry out assessment of the radiological status of the dissolver cell for planning of the future decommissioning/dismantling operations. The dissolver interiors are expected to be contaminated with the dissolution remains of irradiated thorium oxide rods in addition to some of the partially dissolved thoria pellets. Hence, 220 Rn, a daughter product of 228 Th is of major radiological concern. Airborne activity of thoron daughters 212 Pb (Th-B) and 212 Bi (Th-C) was estimated by air sampling followed by high-resolution gamma spectrometry of filter papers. By measuring the full-energy peaks counts in the energy windows of 212 Pb, 212 Bi and 208 Tl, concentrations of thoron progeny in the sampled air were estimated by applying the respective intrinsic peak efficiency factors and suitable correction factors for the equilibration effects of 212 Pb and 212 Bi in the filter paper during the delay between sampling and counting. Then the thoron working level (TWL) was evaluated using the International Commission on Radiological Protection (ICRP) methodology. Finally, the potential effective dose to the workers, due to inhalation of thoron and its progeny during dismantling operations was assessed by using dose conversion factors recommended by ICRP. Analysis of filter papers showed a maximum airborne thoron progeny concentration of 30 TWLs inside the dissolver. (authors)

  19. Integrated FDG-PET/CT vs. standard radiological examinations: Comparison of capability for assessment of postoperative recurrence in non-small cell lung cancer patients

    International Nuclear Information System (INIS)

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

    2010-01-01

    Purpose: The purpose of this study was to prospectively and directly compare diagnostic capabilities of whole-body integrated FDG-PET/CT and standard radiologic examination for assessment of recurrence in postoperative non-small cell lung cancer (NSCLC) patients. Materials and methods: A total of 92 consecutive pathologically diagnosed NSCLC patients (65 males, 27 females; mean age, 71 years) underwent pathologically and surgically proven complete resection, followed by prospective whole-body FDG-PET/CT and standard radiological examinations. Final diagnosis of recurrence was based on the results of more than 1 year of follow-up and/or pathological examinations. On both methods, the probability of recurrence was assessed in each patient by using a five-point visual scoring system, and the each final diagnosis was made by consensus between two readers. Kappa analyses were performed to determine inter-observer agreement for both methods, and ROC analyses were used to compare capability of the two methods for assessment of postoperative recurrence on a per-patient basis. Sensitivity, specificity and accuracy were also compared between PET/CT and standard radiological examination by means of McNemar's test. Results: All inter-observer agreements were almost perfect (integrated PET/CT: κ = 0.89; standard radiological examination: κ = 0.81). There were no statistically significant differences in area under the curve, sensitivity, specificity and accuracy between integrated FDG-PET/CT and standard radiologic examinations (p > 0.05). Conclusion: Integrated FDG-PET/CT can be used for assessment of postoperative recurrence in NSCLC patients with accuracy as good as that of standard radiological examinations.

  20. Integrated FDG-PET/CT vs. standard radiological examinations: Comparison of capability for assessment of postoperative recurrence in non-small cell lung cancer patients

    Energy Technology Data Exchange (ETDEWEB)

    Takenaka, Daisuke [Department of Radiology, Kobe University Graduate School of Medicine, 7-5-2 Kusunoki-cho, Chuo-ku, Kobe, Hyogo 650-0017 (Japan); Ohno, Yoshiharu, E-mail: yosirad@kobe-u.ac.j [Department of Radiology, Kobe University Graduate School of Medicine, 7-5-2 Kusunoki-cho, Chuo-ku, Kobe, Hyogo 650-0017 (Japan); Koyama, Hisanobu [Department of Radiology, Kobe University Graduate School of Medicine, 7-5-2 Kusunoki-cho, Chuo-ku, Kobe, Hyogo 650-0017 (Japan); Nogami, Munenobu [Division of Image-Based Medicine, Institute of Biomedical Research and Innovation, 2-2, Minatojima Minamimachi Chuo-ku, Kobe, Hyogo 650-0047 (Japan); Onishi, Yumiko; Matsumoto, Keiko [Department of Radiology, Kobe University Graduate School of Medicine, 7-5-2 Kusunoki-cho, Chuo-ku, Kobe, Hyogo 650-0017 (Japan); Matsumoto, Sumiaki [Department of Radiology, Kobe University Graduate School of Medicine, 7-5-2 Kusunoki-cho, Chuo-ku, Kobe, Hyogo 650-0017 (Japan); Department of Radiology, University of Yamanashi, 1110 Shimogato, Chuo, Yamanashi, 409-3898 (Japan); Yoshikawa, Takeshi; Sugimura, Kazuro [Department of Radiology, Kobe University Graduate School of Medicine, 7-5-2 Kusunoki-cho, Chuo-ku, Kobe, Hyogo 650-0017 (Japan)

    2010-06-15

    Purpose: The purpose of this study was to prospectively and directly compare diagnostic capabilities of whole-body integrated FDG-PET/CT and standard radiologic examination for assessment of recurrence in postoperative non-small cell lung cancer (NSCLC) patients. Materials and methods: A total of 92 consecutive pathologically diagnosed NSCLC patients (65 males, 27 females; mean age, 71 years) underwent pathologically and surgically proven complete resection, followed by prospective whole-body FDG-PET/CT and standard radiological examinations. Final diagnosis of recurrence was based on the results of more than 1 year of follow-up and/or pathological examinations. On both methods, the probability of recurrence was assessed in each patient by using a five-point visual scoring system, and the each final diagnosis was made by consensus between two readers. Kappa analyses were performed to determine inter-observer agreement for both methods, and ROC analyses were used to compare capability of the two methods for assessment of postoperative recurrence on a per-patient basis. Sensitivity, specificity and accuracy were also compared between PET/CT and standard radiological examination by means of McNemar's test. Results: All inter-observer agreements were almost perfect (integrated PET/CT: {kappa} = 0.89; standard radiological examination: {kappa} = 0.81). There were no statistically significant differences in area under the curve, sensitivity, specificity and accuracy between integrated FDG-PET/CT and standard radiologic examinations (p > 0.05). Conclusion: Integrated FDG-PET/CT can be used for assessment of postoperative recurrence in NSCLC patients with accuracy as good as that of standard radiological examinations.

  1. 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.

  2. Radiological impact assessment of the domestic on-road transportation of radioactive isotope wastes

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Myung Hwan; Hong, Sung Wook; Park, Jin Beak [Korea Radioactive Waste Agency, Technology Institute, Daejeon (Korea, Republic of)

    2016-09-15

    Korea Radioactive Waste Agency (KORAD) began to operate the low and intermediate level radioactive waste disposal facility in Gyeongju and to transport the radioactive waste containing radioactive isotopes from Daejeon to the disposal facility for the first time at 2015. For this radioactive waste transportation, in this study, radiological impact assessment is carried out for workers and public. The dose rate to workers and public during the transportation is estimated with consideration of the transportation scenarios and is compared with the Korean regulatory limit. The sensitivity analysis is carried out by considering both the variation of release ratios of the radioactive isotopes from the waste and the variation of the distances between the radioactive waste drum and worker during loading and unloading of radioactive waste. As for all the transportation scenarios, radiological impacts for workers and public have met the regulatory limits.

  3. 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

  4. Systematic Layout Planning of a Radiology Reporting Area to Optimize Radiologists' Performance.

    Science.gov (United States)

    Benitez, Guilherme Brittes; Fogliatto, Flavio Sanson; Cardoso, Ricardo Bertoglio; Torres, Felipe Soares; Faccin, Carlo Sasso; Dora, José Miguel

    2018-04-01

    Optimizing radiologists' performance is a major priority for managers of health services/systems, since the radiologists' reporting activity imposes a severe constraint on radiology productivity. Despite that, methods to optimize radiologists' reporting workplace layout are scarce in the literature. This study was performed in the Radiology Division (RD) of an 850-bed University-based general hospital. The analysis of the reporting workplace layout was carried out using the systematic layout planning (SLP) method, in association with cluster analysis as a complementary tool in early stages of SLP. Radiologists, architects, and hospital managers were the stakeholders consulted for the completion of different stages of the layout planning process. A step-by-step description of the proposed methodology to plan an RD reporting layout is presented. Clusters of radiologists were defined using types of exams reported and their frequency of occurrence as clustering variables. Sectors with high degree of interaction were placed in proximity in the new RD layout, with separation of noisy and quiet areas. Four reporting cells were positioned in the quiet area, grouping radiologists by subspecialty, as follows: cluster 1-abdomen; cluster 2-musculoskeletal; cluster 3-neurological, vascular and head & neck; cluster 4-thoracic and cardiac. The creation of reporting cells has the potential to limit unplanned interruptions and enhance the exchange of knowledge and information within cells, joining radiologists with the same expertise. That should lead to improvements in productivity, allowing managers to more easily monitor radiologists' performance.

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

    International Nuclear Information System (INIS)

    1975-07-01

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

  6. Urinary C-terminal telopeptide of type II collagen, radiological severity, and functional assessment in knee osteoarthritis: are these related?

    Directory of Open Access Journals (Sweden)

    Hayam M Abdel Ghany

    2016-01-01

    Conclusion This study further confirms that urinary CTX-II is an index of early cartilage degradation in knee OA even before radiological changes occurs. The functional assessment using the WOMAC is an easy inexpensive method in reflecting cartilage degradation. Moreover, this work supports the lack of association between the functional status of knee OA patients assessed using the WOMAC and their radiological severity measured using the Kellgren-Lawrence grading scale.

  7. Performance of Models in Radiological Impact Assessment for Normal Operation. Report of Working Group 1 Reference Methodologies for Controlling Discharges of Routine Releases of EMRAS II Topical Heading Reference Approaches for Human Dose Assessment. Environmental Modelling for Radiation Safety (EMRAS II) Programme

    International Nuclear Information System (INIS)

    2017-01-01

    This publication provides the results from Working Group 1, on Reference Methodologies for Controlling Discharges of Routine Releases, of the IAEA’s EMRAS II (Environmental Modelling for Radiation Safety) programme, which ran from 2009 to 2011. This Working Group carried out an intercomparison of methods used for assessing radiological impacts to people and the environment due to authorized releases of radionuclides during normal operation of nuclear facilities. Three important types of exposure scenarios were considered, those related to atmospheric, marine and river releases. The publication describes the details of the hypothetical radioactive release scenarios, the environmental pathways considered, the environmental transfer models applied, the calculation methods and the results obtained. An analysis of the results and the main findings and conclusions relevant for the use of the described input data and methodologies in regulatory applications is included. The publication also presents considerations on selection of the ‘representative person’ and a summary of the different approaches in some States for the regulatory control of radioactive discharges. Input data is included in the annex.

  8. 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)

  9. Determining the suitability of materials for disposal at sea under the London Convention 1972: A radiological assessment procedure

    International Nuclear Information System (INIS)

    2003-10-01

    on conducting specific assessments to determine whether candidate materials for disposal at sea contained de minimis levels of radioactivity. This report contains guidance on performing specific assessments of candidate materials to determine whether the materials are de minimis in the meaning of the London Convention 1972. It follows the guidelines adopted by the Twenty-first Consultative Meeting of the London Convention 1972 that incorporate a Stepwise Evaluation Procedure for screening candidate material to determine if it can be treated as 'non-radioactive' (i.e. de minimis) under the Convention. Material that cannot be readily defined as de minimis on the basis of Steps 1 to 5 of the Stepwise Evaluation Procedure require a specific assessment at Step 6. Such an assessment is the subject of this report. The assessment process described in this report is based on an inherently conservative procedure consistent with the precautionary approach, provided for under the London Convention 1972. Its purpose is to ensure the use of conservative models and cautious assumptions that result in the overestimation of the doses due to candidate materials that might be disposed of at sea in near coastal waters under de minimis provisions. Accordingly, the radiological consequences of disposal at sea of de minimis materials in other areas of the continental shelf and deeper waters will result in much lower radiation exposures than those considered here. It must be stressed that any candidate materials designated as de minimis must comply with all other provisions of the Convention. Section 2 provides a summary of the Stepwise Evaluation Procedure as detailed in the guidelines and background information necessary to understand the context of this guidance. Section 3 describes in detail a procedure to conduct the specific radiological assessment of the disposal of a candidate material. It contains a schematic diagram illustrating the specific assessment process and components of

  10. Idaho National Engineering Laboratory Radiological Control Performance Indicator Report. Fourth quarter -- year-end report, Calendar year 1995

    International Nuclear Information System (INIS)

    Reavis, R.

    1996-03-01

    The INEL Radiological Control Performance Indicator Report is comprised of a description of the indicator and the criteria used for measurement. Indicators evaluated in this report include: collective radiation dose; average worker radiation dose; maximum radiation dose to a worker; maximum neutron dose to a worker; number of skin contaminations; number of clothing contaminations; airborne events; total radiological intakes; contamination areas; high contamination area; airborne radioactivity area; and radioactive spills

  11. Performance assessment - risk assessment vive la differences

    International Nuclear Information System (INIS)

    Nitschke, R.L.

    1997-01-01

    In the sister worlds of radioactive waste management disposal and environmental restoration, there are two similar processes and computational approaches for determining the acceptability of the proposed activities. While similar, these two techniques can lead to confusion and misunderstanding if the differences are not recognized and appreciated. In the case of radioactive waste management, the performance assessment process is used to determine compliance with certain prescribed 'performance objectives'. These objectives are designed to ensure that the disposal of radioactive (high-level, low-level, and/or transuranic) waste will be protective of human health and the environment. The environmental link is primarily through assuring protection of the groundwater as a resource. In the case of environmental restoration, the risk assessment process is used to determine the proper remedial action response, if any, for a past hazardous waste release. The process compares the 'no action' or 'leave as is' option with both carcinogenic and noncarcinogenic values for human health to determine the need for any action and to help to help determine just what the appropriate action would need to be. The impacts to the ecological system are evaluated in a slightly, different but similar fashion. Now the common objectives between these two processes notwithstanding. There are some key and fundamental differences that need to be answered that make direct comparisons or a common approach inappropriate. Failure to recognize this can lead to confusion and misunderstanding. This can be particularly problematic when one is faced with an active disposal facility located within the boundaries of an environmental restoration site as is the case at the Idaho National Engineering Laboratory (INEL). Through a critical evaluation of the performance assessment and risk assessment processes, highlighting both similarities and differences, it is hoped that greater understanding and appreciation

  12. Assessment of the radiological impact of the inactive uranium-mill tailings at Shiprock, New Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Haywood, F.F.; Goldsmith, W.A.; Lantz, P.M.; Fox, W.F.; Shinpaugh, W.H.; Hubbard, H.M. Jr.

    1979-12-01

    Uranium-mill tailings at an inactive site near Shiprock, New Mexico, contain an estimated 950 curies (Ci) of /sup 226/Ra together with its radioactive daughters. A radiological survey was conducted at this site in February 1976. Decontamination work and tailings stabilization performed at the site since that time have greatly changed conditions there and little effort was applied to quantification of potential health effects in comparison to the earlier consideration of the site at Salt Lake City. The present report delineates the radiological conditions that existed at the time of the survey including information on the surface and below-surface distribution of /sup 226/Ra. The data presented support the conclusion that diffusion of radon and inhalation of radon daughters is the principal mode of exposure of offsite population groups.

  13. Assessment of the radiological impact of the inactive uranium-mill tailings at Shiprock, New Mexico

    International Nuclear Information System (INIS)

    Haywood, F.F.; Goldsmith, W.A.; Lantz, P.M.; Fox, W.F.; Shinpaugh, W.H.; Hubbard, H.M. Jr.

    1979-12-01

    Uranium-mill tailings at an inactive site near Shiprock, New Mexico, contain an estimated 950 curies (Ci) of 226 Ra together with its radioactive daughters. A radiological survey was conducted at this site in February 1976. Decontamination work and tailings stabilization performed at the site since that time have greatly changed conditions there and little effort was applied to quantification of potential health effects in comparison to the earlier consideration of the site at Salt Lake City. The present report delineates the radiological conditions that existed at the time of the survey including information on the surface and below-surface distribution of 226 Ra. The data presented support the conclusion that diffusion of radon and inhalation of radon daughters is the principal mode of exposure of offsite population groups

  14. Power performance assessment. Final report

    International Nuclear Information System (INIS)

    Frandsen, S.

    1998-12-01

    In the increasingly commercialised wind power marketplace, the lack of precise assessment methods for the output of an investment is becoming a barrier for wider penetration of wind power. Thus, addressing this problem, the overall objectives of the project are to reduce the financial risk in investment in wind power projects by significantly improving the power performance assessment methods. Ultimately, if this objective is successfully met, the project may also result in improved tuning of the individual wind turbines and in optimisation methods for wind farm operation. The immediate, measurable objectives of the project are: To prepare a review of existing contractual aspects of power performance verification procedures of wind farms; to provide information on production sensitivity to specific terrain characteristics and wind turbine parameters by analyses of a larger number of wind farm power performance data available to the proposers; to improve the understanding of the physical parameters connected to power performance in complex environment by comparing real-life wind farm power performance data with 3D computational flow models and 3D-turbulence wind turbine models; to develop the statistical framework including uncertainty analysis for power performance assessment in complex environments; and to propose one or more procedures for power performance evaluation of wind power plants in complex environments to be applied in contractual agreements between purchasers and manufacturers on production warranties. Although the focus in this project is on power performance assessment the possible results will also be of benefit to energy yield forecasting, since the two tasks are strongly related. (au) JOULE III. 66 refs.; In Co-operation Renewable Energy System Ltd. (GB); Centre for Renewable Energy (GR); Aeronautic Research Centre (SE); National Engineering Lab. (GB); Public Power Cooperation (GR)

  15. 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)

  16. 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

  17. Radiological impact assessment on non-human species from the radioactive waste disposal

    International Nuclear Information System (INIS)

    Gil Castillo, Reinaldo; Peralta Vital, Jose L.; Leiva Bombuse, Dennys

    2008-01-01

    The paper shows the use of a methodology in order to carry out the radiological impact assessment in non-human species (animals and plants) from a planned radioactive waste disposal facility. The application of modelling tools to simulate the behaviour (release and transport) of the radionuclides through the engineered barriers and the geosphere, and its final access to the soil and a river are described too. To evaluate the compliance with the adopted biota dose limits, were used the calculated maximum radionuclide concentrations for different environmental compartments (water, soil and sediment). Preliminary, the results showed that the Radiological Biota impacts are acceptable according to the adopted criteria (Radionuclides concentrations below the Biota Concentration Guides). The results showed that according theirs impact the more important radionuclides were: 241 Am/ 226 Ra/ 137 Cs/ 60 Co. The Riparian animals were the more exposed Biota organism. The results support the decision making process since could be identified the relevant radiological impact in the environment (plants and animals) near to a disposal facility (real or planned). Also the paper identified methodological tools useful to evaluate the site acceptance, for the early stages of disposal facilities (site selection process, licensing, etc), in absence of real data of radionuclides concentrations in the environment. (author)

  18. Natural language processing using online analytic processing for assessing recommendations in radiology reports.

    Science.gov (United States)

    Dang, Pragya A; Kalra, Mannudeep K; Blake, Michael A; Schultz, Thomas J; Stout, Markus; Lemay, Paul R; Freshman, David J; Halpern, Elkan F; Dreyer, Keith J

    2008-03-01

    The study purpose was to describe the use of natural language processing (NLP) and online analytic processing (OLAP) for assessing patterns in recommendations in unstructured radiology reports on the basis of patient and imaging characteristics, such as age, gender, referring physicians, radiology subspecialty, modality, indications, diseases, and patient status (inpatient vs outpatient). A database of 4,279,179 radiology reports from a single tertiary health care center during a 10-year period (1995-2004) was created. The database includes reports of computed tomography, magnetic resonance imaging, fluoroscopy, nuclear medicine, ultrasound, radiography, mammography, angiography, special procedures, and unclassified imaging tests with patient demographics. A clinical data mining and analysis NLP program (Leximer, Nuance Inc, Burlington, Massachusetts) in conjunction with OLAP was used for classifying reports into those with recommendations (I(REC)) and without recommendations (N(REC)) for imaging and determining I(REC) rates for different patient age groups, gender, imaging modalities, indications, diseases, subspecialties, and referring physicians. In addition, temporal trends for I(REC) were also determined. There was a significant difference in the I(REC) rates in different age groups, varying between 4.8% (10-19 years) and 9.5% (>70 years) (P OLAP revealed considerable differences between recommendation trends for different imaging modalities and other patient and imaging characteristics.

  19. Final Radiological Assessment of External Exposure for CLEAR-Line Americium Recovery Operations

    Energy Technology Data Exchange (ETDEWEB)

    Davis, Adam C. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Belooussova, Olga N. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Hetrick, Lucas Duane [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-11-12

    Los Alamos National Laboratory is currently planning to implement an americium recovery program. The americium, ordinarily isotopically pure 241Am, would be extracted from existing Pu materials, converted to an oxide and shipped to support fabrication of americium oxide-beryllium neutron sources. These operations would occur in the currently proposed Chloride Extraction and Actinide Recovery (CLEAR) line of glove boxes. This glove box line would be collocated with the currently-operational Experimental Chloride Extraction Line (EXCEL). The focus of this document is to provide an in-depth assessment of the currently planned radiation protection measures and to determine whether or not further design work is required to satisfy design-goal and ALARA requirements. Further, this document presents a history of americium recovery operations in the Department of Energy and high-level descriptions of the CLEAR line operations to provide a basis of comparison. Under the working assumptions adopted by this study, it was found that the evaluated design appears to mitigate doses to a level that satisfies the ALARA-in-design requirements of 10 CFR 835 as implemented by the Los Alamos National Laboratory procedure P121. The analyses indicate that extremity doses would also meet design requirements. Dose-rate calculations were performed using the radiation transport code MCNP5 and doses were estimated using a time-motion study developed in consort with the subject matter expert. A copy of this report and all supporting documentation are located on the Radiological Engineering server at Y:\\Rad Engineering\\2013 PROJECTS\\TA-55 Clear Line.

  20. Image quality assessment using the CD-DISC phantom for vascular radiology and vascular surgery

    International Nuclear Information System (INIS)

    Struelens, Lara; Hambach, Lionel; Buls, Nico; Smans, Kristien; Malchair, Francoise; Hoornaert, Marie-Therese; Vanhavere, Filip; Bosmans, Hilde

    2008-01-01

    The purpose of the study was to evaluate image quality (IQ) associated with vascular radiology and vascular surgery procedures in Belgium and to determine reference values for future image quality assessment. IQ was evaluated with the CD-DISC contrast-detail phantom. This circular PMMA phantom contains 225 holes with different diameter and depth, to quantify resolution and contrast. Images of the phantom were acquired for both fluoroscopy and subtraction images on 21 systems. Three observers evaluated the images by determining the threshold contrast visible for every diameter. This results in contrast-detail curves and image quality figures. We observed a large difference in IQ between the centres. No straightforward correlation could be found with radiation dose or other exposure settings. A comparison was made with the image quality evaluation of the systems performed with the TOR[18FG] phantom for fluoroscopy. There is no clear correlation observed between the results of the CD-DISC phantom and the TOR phantom. However, systems with very poor or very good image quality could be detected by both phantoms. An important result is that a 75th percentile reference contrast-detail curve could be proposed to separate the best centres from these with poorer quality. Some centres had also a significantly better image quality than others. Therefore, we introduced also a 25th percentile. Centres with IQ above this value are recommended to lower the dose and work with acceptable rather than excellent image quality. The CD-DISC phantom thus allows to guide the image quality setting

  1. A comparison of radiological risk assessment models: Risk assessment models used by the BEIR V Committee, UNSCEAR, ICRP, and EPA (for NESHAP)

    International Nuclear Information System (INIS)

    Wahl, L.E.

    1994-03-01

    Radiological risk assessments and resulting risk estimates have been developed by numerous national and international organizations, including the National Research Council's fifth Committee on the Biological Effects of Ionizing Radiations (BEIR V), the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR), and the International Commission on Radiological Protection (ICRP). A fourth organization, the Environmental Protection Agency (EPA), has also performed a risk assessment as a basis for the National Emission Standards for Hazardous Air Pollutants (NESHAP). This paper compares the EPA's model of risk assessment with the models used by the BEIR V Committee, UNSCEAR, and ICRP. Comparison is made of the values chosen by each organization for several model parameters: populations used in studies and population transfer coefficients, dose-response curves and dose-rate effects, risk projection methods, and risk estimates. This comparison suggests that the EPA has based its risk assessment on outdated information and that the organization should consider adopting the method used by the BEIR V Committee, UNSCEAR, or ICRP

  2. PERFORMANCE ASSESSMENT FOR FIELD SPORTS

    Directory of Open Access Journals (Sweden)

    Christopher Carling

    2009-03-01

    Full Text Available DESCRIPTION The book covers the various sport science assessment procedures for sports such as soccer, rugby, field hockey and lacrosse. It provides detailed and clear information about laboratory and field-based methods that can be used to assess and improve both individual and team performance. PURPOSE The book aims to provide a contemporary reference tool for selection of appropriate testing procedures for sports across a range of scientific disciplines. FEATURES The text begins with a chapter on the rationales for performance assessments, the use of technology and the necessity for procedures to conform to scientific rigor, explaining the importance of test criteria. This chapter ends by emphasizing the importance of the feedback process and vital considerations for the practitioner when interpreting the data, selecting which information is most important and how to deliver this back to the athlete or coach in order to deliver a positive performance outcome. The next two chapters focus on psychological assessments with respect to skill acquisition, retention and execution providing a variety of qualitative and quantitative options, underpinned with scientific theory and contextualized in order to improve the understanding of the application of these methods to improve anticipation and decision-making to enhance game intelligence.Chapter 4 provides coverage of match analysis techniques in order to make assessments of technical, tactical and physical performances. Readers learn about a series of methodologies ranging from simplistic pen and paper options through to sophisticated technological systems with some exemplar data also provided. Chapters 5 through 7 cover the physiological based assessments, including aerobic, anaerobic and anthropometric procedures. Each chapter delivers a theoretical opening section before progressing to various assessment options and the authors make great efforts to relate to sport-specific settings. The final

  3. Assessment of the radiological protection aspects of disposal of high level waste on the ocean floor

    International Nuclear Information System (INIS)

    Grimwood, P.D.; Webb, G.A.M.

    1976-10-01

    This study is a preliminary assessment of the potential radiological consequences of disposal of solidified high-level radioactive waste on the floor of the deep ocean. As an input to the modelling used in the assessment, an arbitrary choice is made to consider the total high-level waste which would be generated by a postulated world nuclear power programme to the year 2000. It is assumed that all this waste, in solidified form, is disposed of on to the floor of the North Atlantic. The body of this report is the modelling of the subsequent release of activity into the water, its dispersion in the ocean and eventual uptake in marine organisms and sediments. The consequent radiation exposure of man is assessed in terms of both individual and collective doses. It is intended that only broad conclusions should be drawn from this study. The objective of the assessment is to highlight those subject areas where more study of information is required before a decision can be reached regarding this method of disposal. No overriding reason connected with the radiological protection considerations has been identified which would preclude the disposal of suitably conditioned high-level waste on the ocean floor. Further evaluation of this disposal option is therefore justified. (author)

  4. Comparison between Two Radiological Methods for Assessment of Tooth Root Resorption: An In Vitro Study

    Directory of Open Access Journals (Sweden)

    Sabina Saccomanno

    2018-01-01

    Full Text Available Purpose. This study aims to verify the validity of the radiographic image and the most effective radiological techniques for the diagnosis of root resorption to prevent, cure, and reduce it and to verify if radiological images can be helpful in medical and legal situations. Methods. 19 dental elements without root resorption extracted from several patients were examined: endooral and panoramic radiographs were performed, with traditional and digital methods. Then the root of each tooth was dipped into 3-4 mm of 10% nitric acid for 24 hours to simulate the resorption of the root and later submitted again to radiological examinations and measurements using the same criteria and methods. Results. For teeth with root resorption the real measurements and the values obtained with endooral techniques and digital sensors are almost the same, while image values obtained by panoramic radiographs are more distorted than the real ones. Conclusions. Panoramic radiographs are not useful for the diagnosis of root resorption. The endooral examination is, in medical and legal fields, the most valid and objective instrument to detect root resorption. Although the literature suggests that CBCT is a reliable tool in detecting root resorption defects, the increased radiation dosage and expense and the limited availability of CBCT in most clinical settings accentuate the outcome of this study.

  5. Introductory lecture series for first-year radiology residents: implementation, investment and assessment.

    Science.gov (United States)

    Chapman, Teresa; Chew, Felix S

    2013-03-01

    A lecture series aimed at providing new radiology residents a rapid course on the fundamental concepts of professionalism, safety, and interpretation of diagnostic imaging was established. Evaluation of the course's educational value was attempted through surveys. Twenty-six live 45-minute lectures presented by 16 or 17 faculty members were organized exclusively for the first class of radiology residents, held over a 2-month period at the beginning of certain weekdays. Online surveys were conducted after the course to gather feedback from residents. Average resident rotation evaluation scores were measured over the first semester for the two classes before and after this new course implementation. The lecture series was successfully organized and implemented. A total of 33 residents sat through the course over three summers. Faculty reported a reasonable number of preparation hours, and 100% of residents indicated they valued the course. Comparison of class average evaluation scores before and after the existence of this 2-month course did not significantly change. This collection of introductory lectures on professionalism, safety, and diagnostic imaging, delivered early in the first year of the radiology residency, requires a reasonable number of invested preparation hours by the faculty but results in a universal increase in resident confidence. However, we were unable to demonstrate an objective improvement in resident performance on clinical rotations. Copyright © 2013 AUR. Published by Elsevier Inc. All rights reserved.

  6. Quality initiatives: lean approach to improving performance and efficiency in a radiology department.

    Science.gov (United States)

    Kruskal, Jonathan B; Reedy, Allen; Pascal, Laurie; Rosen, Max P; Boiselle, Phillip M

    2012-01-01

    Many hospital radiology departments are adopting "lean" methods developed in automobile manufacturing to improve operational efficiency, eliminate waste, and optimize the value of their services. The lean approach, which emphasizes process analysis, has particular relevance to radiology departments, which depend on a smooth flow of patients and uninterrupted equipment function for efficient operation. However, the application of lean methods to isolated problems is not likely to improve overall efficiency or to produce a sustained improvement. Instead, the authors recommend a gradual but continuous and comprehensive "lean transformation" of work philosophy and workplace culture. Fundamental principles that must consistently be put into action to achieve such a transformation include equal involvement of and equal respect for all staff members, elimination of waste, standardization of work processes, improvement of flow in all processes, use of visual cues to communicate and inform, and use of specific tools to perform targeted data collection and analysis and to implement and guide change. Many categories of lean tools are available to facilitate these tasks: value stream mapping for visualizing the current state of a process and identifying activities that add no value; root cause analysis for determining the fundamental cause of a problem; team charters for planning, guiding, and communicating about change in a specific process; management dashboards for monitoring real-time developments; and a balanced scorecard for strategic oversight and planning in the areas of finance, customer service, internal operations, and staff development. © RSNA, 2012.

  7. Effect of Massed Versus Interleaved Teaching Method on Performance of Students in Radiology.

    Science.gov (United States)

    Rozenshtein, Anna; Pearson, Gregory D N; Yan, Sherry X; Liu, Andrew Z; Toy, Dennis

    2016-08-01

    Radiology instruction is based on the principle that grouped (or massed) repetition of an intellectual activity leads to expertise. The aim of this study was to test the hypothesis that the spaced (or interleaved) method of teaching chest x-ray interpretation is more effective than the massed method. After institutional review board approval was obtained, 40 first- and second-year medical students were randomized into two groups matched by age, gender, and education experience. Both groups saw six examples of 12 common chest radiographic patterns, one grouped, the other scrambled randomly without repeating strings. After a distraction, participants took a multiple-choice test consisting of two cases in each radiographic pattern, one previously shown, one new. Results were analyzed using two-tailed Student's t test of proportion. Comparing interleaved and massed groups, the average overall score was 57% versus 43% (P = .03), the recollection score was 61% versus 47% (P = .03), and the induction score was 53% versus 40% (P = 0.10), respectively. Comparing second- and first-year students, average scores were 67% and 39%, respectively (P method of instruction leads to better results than the massed method across all levels of education. A higher level of medical education improves performance independent of method of instruction. Copyright © 2016 American College of Radiology. Published by Elsevier Inc. All rights reserved.

  8. 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

  9. Federal Radiological Monitoring and Assessment Center advanced part phase response actions

    International Nuclear Information System (INIS)

    Hurley, B.

    1997-01-01

    Federal Radiological Monitoring and Assessment Center (FRMAC) response actions are carried out in Advance Party and Main Party phases of deployment. Response activities are initiated by a FRMAC Home Team prior to and during Advance Party deployment, with Home Team support continuing until the FRMAC Main Party is fully deployed. Upon arrival at the incident scene, the Advance Party establishes communications with other federal, state, and local response organizations, Following an Advance Party Meeting with these response organizations, FRMAC begins formulation of an initial monitoring and sampling plan, in coordination with the jurisdictional state and the Lead Federal Agency, and initiates detailed logistical arrangements for Main Party deployment and operations

  10. 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

  11. Perspectives on dosimetric uncertainties and radiological assessments of radioactive waste management

    International Nuclear Information System (INIS)

    Smith, G.M.; Pinedo, P.; Cancio, D.

    1997-01-01

    The purpose of this paper is to raise some issues concerning uncertainties in the estimation of doses of ionizing radiation arising from waste management practices and the contribution to those uncertainties arising from dosimetry modelling. The intentions are: (a) to provide perspective on the relative uncertainties in the different aspects of radiological assessments of waste management; (b) to give pointers as to where resources could best be targeted as regards reduction in overall uncertainties; and (c) to provide regulatory insight to decisions on low dose management as related to waste management practices. (author)

  12. Disposal of radioactive waste in evaporite formations - a review of published radiological assessments and their relevance to the UK

    International Nuclear Information System (INIS)

    Lawson, G.

    1983-11-01

    Radiological assessments of the disposal of radioactive waste in evaporite formations, principally halite, have been reviewed. These assessments were carried out in the USA, the Netherlands, Denmark and West Germany. The general nature of evaporite formations in the UK is discussed and comments are given on the broad relevance of the assessments to the potential disposal of radioactive waste in UK evaporite formations. (author)

  13. 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

  14. Methodology for NDA performance assessment

    International Nuclear Information System (INIS)

    Cuypers, M.; Franklin, M.; Guardini, S.

    1986-01-01

    In the framework of the RandD programme of the Joint Research Centre of the Commission of the European Communities, a considerable effort is being dedicated to performance assessment of NDA techniques taking account of field conditions. By taking account of field conditions is meant measurement samples of the size encountered in practice and training which allows inspectors to design cost efficient verification plans for the real situations encountered in the field. Special laboratory facilities referred to as PERLA are being constructed for this purpose. These facilities will be used for measurement experiments and for training. In this paper, performance assessment is discussed under the headings of measurement capability and in-field effectiveness. Considerable emphasis is given to the role of method specific measurement error models. The authors outline the advantages of giving statistical error models a sounder basis in the physical phenomenology of the measurement method

  15. Preliminary melter performance assessment report

    International Nuclear Information System (INIS)

    Elliott, M.L.; Eyler, L.L.; Mahoney, L.A.; Cooper, M.F.; Whitney, L.D.; Shafer, P.J.

    1994-08-01

    The Melter Performance Assessment activity, a component of the Pacific Northwest Laboratory's (PNL) Vitrification Technology Development (PVTD) effort, was designed to determine the impact of noble metals on the operational life of the reference Hanford Waste Vitrification Plant (HWVP) melter. The melter performance assessment consisted of several activities, including a literature review of all work done with noble metals in glass, gradient furnace testing to study the behavior of noble metals during the melting process, research-scale and engineering-scale melter testing to evaluate effects of noble metals on melter operation, and computer modeling that used the experimental data to predict effects of noble metals on the full-scale melter. Feed used in these tests simulated neutralized current acid waste (NCAW) feed. This report summarizes the results of the melter performance assessment and predicts the lifetime of the HWVP melter. It should be noted that this work was conducted before the recent Tri-Party Agreement changes, so the reference melter referred to here is the Defense Waste Processing Facility (DWPF) melter design

  16. Methods for assessing the long term radiological consequences of radionuclide entry into groundwater

    International Nuclear Information System (INIS)

    Maul, P.R.

    1983-01-01

    The methods have been developed to model the transport of radionuclides in groundwater, based on an analytical approach to the governing transport equations, are sufficiently general to enable assessments to be made of the long term radiological significance of groundwater contamination for a range of possible problems. Although the methods are not as flexible as those based on numerical solutions of the transport equations, they have several advantages, including reduced computing time. The methods described can be used to identify critical parameters and assess the significance of data uncertainties in ground-water transport calculations. Such an analysis, combined with experimental measurements where necessary, can provide a sound basis for assessing potential radiation hazards. (U.K.)

  17. Performance assessment review for DOE LLW disposal facilities

    International Nuclear Information System (INIS)

    Wilhite, Elmer L.

    1992-01-01

    The United States Department of Energy (US DOE) disposes of low-level radioactive waste in near-surface disposal facilities. Safety of the disposal operations is evaluated for operational safety as well as long-term safety. Operational safety is evaluated based on the perceived level of hazard of the operation and may vary from a simple safety assessment to a safety analysis report. Long-term safety of all low-level waste disposal systems is evaluated through the conduct of a radiological performance assessment. The US DOE has established radiological performance objectives for disposal of low-level waste. They are to protect a member of the general public from receiving over 25 mrem/y, and an inadvertent intruder into the waste from receiving over 100 mrem/y continuous exposure or 500 mrem from a single exposure. For a disposal system to be acceptable, a performance assessment must be prepared which must be technically accurate and provide reasonable assurance that these performance objectives are met. Technical quality of the performance assessments is reviewed by a panel of experts. The panel of experts is used in two ways to assure the technical quality of performance assessment. A preliminary (generally 2 day) review by the panel is employed in the late stages of development to provide guidance on finalizing the performance assessment. The comments from this review are communicated to the personnel responsible for the performance assessment for consideration and incorporation. After finalizing the performance assessment, it is submitted for a formal review. The formal review is accomplished by a much more thorough analysis of the performance assessment over a multi-week time period. The panel then formally reports their recommendations to the US DOE waste management senior staff who make the final determination on acceptability of the performance assessment. A number of lessons have been learned from conducting several preliminary reviews of performance

  18. Performance Assessment Institute-NV

    Energy Technology Data Exchange (ETDEWEB)

    Lombardo, Joesph [Univ. of Nevada, Las Vegas, NV (United States)

    2012-12-31

    The National Supercomputing Center for Energy and the Environment’s intention is to purchase a multi-purpose computer cluster in support of the Performance Assessment Institute (PA Institute). The PA Institute will serve as a research consortium located in Las Vegas Nevada with membership that includes: national laboratories, universities, industry partners, and domestic and international governments. This center will provide a one-of-a-kind centralized facility for the accumulation of information for use by Institutions of Higher Learning, the U.S. Government, and Regulatory Agencies and approved users. This initiative will enhance and extend High Performance Computing (HPC) resources in Nevada to support critical national and international needs in "scientific confirmation". The PA Institute will be promoted as the leading Modeling, Learning and Research Center worldwide. The program proposes to utilize the existing supercomputing capabilities and alliances of the University of Nevada Las Vegas as a base, and to extend these resource and capabilities through a collaborative relationship with its membership. The PA Institute will provide an academic setting for interactive sharing, learning, mentoring and monitoring of multi-disciplinary performance assessment and performance confirmation information. The role of the PA Institute is to facilitate research, knowledge-increase, and knowledge-sharing among users.

  19. Radiological field survey problems and solutions

    International Nuclear Information System (INIS)

    Deming, E.J.; Boerner, A.J.

    1986-01-01

    Situations often arise during radiological field surveys which require the health physicist to improvise and/or make spot decisions. At times these situations can be humorous, but they can also present hazards more serious than normal radiological considerations. This presentation will depict various problematic situations encountered by Oak Ridge Associated Universities Radiological Site Assessment Program in the course of performing field environmental surveys. Detailing these potential hazards can alert other field survey groups to problems they may encounter

  20. Performance assessment plans and methods for the Salt Repository Project

    International Nuclear Information System (INIS)

    1984-08-01

    This document presents the preliminary plans and anticipated methods of the Salt Repository Project (SRP) for assessing the postclosure and radiological aspects of preclosure performance of a nuclear waste repository in salt. This plan is intended to be revised on an annual basis. The emphasis in this preliminary effort is on the method of conceptually dividing the system into three subsystems (the very near field, the near field, and the far field) and applying models to analyze the behavior of each subsystem and its individual components. The next revision will contain more detailed plans being developed as part of Site Characterization Plan (SCP) activities. After a brief system description, this plan presents the performance targets which have been established for nuclear waste repositories by regulatory agencies (Chapter 3). The SRP approach to modeling, including sensitivity and uncertainty techniques is then presented (Chapter 4). This is followed by a discussion of scenario analysis (Chapter 5), a presentation of preliminary data needs as anticipated by the SRP (Chapter 6), and a presentation of the SRP approach to postclosure assessment of the very near field, the near field, and the far field (Chapters 7, 8, and 9, respectively). Preclosure radiological assessment is discussed in Chapter 10. Chapter 11 presents the SRP approach to code verification and validation. Finally, the Appendix lists all computer codes anticipated for use in performance assessments. The list of codes will be updated as plans are revised

  1. Radiological assessment of long-term effects at the Semipalatinsk test site. NATO-Semipalatinsk Project 1995/96

    International Nuclear Information System (INIS)

    Hill, P.; Hille, R.; Bouisset, P.; Calmet, D.; Kluson, J.; Smagulov, S.; Sysebaev, A.

    1996-12-01

    To determine the long-term consequences of atmospheric atomic bomb tests for the population in the surroundings of the former nuclear weapons test site near Semipalatinsk, studies were performed by international cooperation between Kazakh, French, Czech and German institutions at two measuring locations (Moistik, Maisk) in Kazakhstan. Moistik is a village close to Dolon and downwind of the first atomic bomb explosion on August 29, 1947. Maisk is close to Kurchatov and not too far from ground zero. With financial support from NATO, nine experts from Europe went on a field mission to Kazakhstan in September 1995 to assess, together with Kazakh scientists, the radiological situation as far as external doses, environmental contamination and body burden of man are concerned. The results show that surface contamination from nuclear weapons tests has in the meantime decayed to a large extent. External doses largely correspond to the natural background. The remaining incorporation of longer-lived radionuclides is also slight and in 1995 merely led to an annual dose of less than 1% of the natural radiation exposure for 137 Cs and 90 Sr. The question of a dose contribution by the possible incorporation of 239 Pu remains open. Life in the villages of Maisk and Moistik does not currently involve any radiological threat to the inhabitants. However, dose reconstruction for the older inhabitants directly affected by aboveground atomic weapons tests remains difficult. (orig.)

  2. Technical quality assessment of breast ultrasound according to American College of Radiology (ACR) Standards

    International Nuclear Information System (INIS)

    Ko, Kyung Hee; Kim, Eun Kyung; Kim, Young Ah; Son, Eun Ju; Oh, Ki Keun; Chung, Sun Yang

    2003-01-01

    To evaluate the technical quality of breast ultrasound based on American College of Radiology(ACR) standards. Between March 2002 and July 2002, ninety three breast sonograms obtained from 73 institutions were evaluated based on ACR standards for the hardware, technical settings, labeling of the images and identification. Of 93 breast sonograms, a satisfactory compliance with all ACR standards in the performance of breast US examinations was documented in 31% while the remaining 69% did not fully meet all ACR standards. 4.3% of breast US examinations were performed with a convex transducers, and the focal zone was inappropriately positioned in 14.2%. Gray-scale gain was subjectively characterized as inappropriate in 26.9%, and the size of lesion was not measured in 7.5%. Anatomic location of lesions was inappropriately described in 9.3%. The orientation of an US transducer was not properly labeled on any images in 33.3%. Inadequate recording of patient's information was noted in 43.3%. 50% of sonograms at University medical centers and larger general hospitals fully met all ACR standards while 36.8% at radiologic clinics and 12.1% at other private clinics met all ACR standards. Overall, 69% of breast sonograms failed to meet the quality criteria of the ACR standards. Therefore, it is essential to educate the basic technical details in performing breast US for the quality control.

  3. Training program for radiologic technologists for performing chest X-rays at inspiration in uncooperative children

    International Nuclear Information System (INIS)

    Langen, Heinz Jakob; Muras, S.; Kohlhauser-Vollmuth, C.; Stenzel, M.; Beer, M.

    2009-01-01

    A computer program was created to train technologists to perform chest X-rays in crying infants at maximum inspiration. Videos of 4 children were used. Using a computer program, the moment of deepest inspiration was determined in the video in the single frame view. During the normal running video, 14 technologists (3 with significant experience, 3 with little experience and 8 with very little experience in pediatric radiography) simulated a chest radiograph by pushing a button. The computer program stopped the video and the period of time to the optimal moment for a chest x-ray was calculated. Every technologist simulated 10 chest X-rays in each of the 4 video clips. The technologists then trained themselves to perform chest X-rays at optimal inspiration like playing a computer game. After training, the test was repeated. Changes were evaluated by t-test for unpaired samples (level of significance p < 0.05). Although the differences improved in all children, minimal deviation from the optimal moment for taking an X-ray at inspiration occurred in the periodically crying child (0.21 sec before and 0.13 sec after training). In a non-periodically crying infant, the largest differences were shown. The values improved significantly from 0.29 sec to 0.22 sec. The group with substantial experience in pediatric radiology improved significantly from 0.22 sec to 0.15 sec. The group with very little experience in pediatric radiology showed worse results (improvement from 0.29 sec to 0.21 sec). (orig.)

  4. Radiological assessment of the breast following enhancement with Macrolane: Managing the challenges

    International Nuclear Information System (INIS)

    Scaperrotta, Gianfranco; Satchithananda, Keshtra; Tengvar, Magnus; Post, Karin; Lim, Adrian K.; Panizza, Pietro; Wesolowska, Ewa; Inglefield, Christopher J.

    2017-01-01

    Highlights: • Macrolane VRF ® , a biodegradable, stabilized hyaluronic acid gel, was used for breast enhancement 2008–2012. • Even after more than 4 years, small amounts of Macrolane can still be visible on magnetic resonance imaging (MRI) or ultrasound in some patients similar to permanent implants, the presence of Macrolane gel may interfere with interpretation of mammography. • Knowledge of the product’s appearance on radiological assessment of breasts following Macrolane treatment is therefore required. • It is possible to assess the vast majority of patients using a combination of digital mammography and ultrasonography examination. - Abstract: Macrolane VRF ® , a biodegradable, stabilized hyaluronic acid gel, was used for breast enhancement 2008–2012. Similar to permanent implants, the presence of Macrolane gel may interfere with interpretation of mammography. This short communication aims to provide a guide to the appearance of Macrolane on radiology examination (including mammography, ultrasound and magnetic resonance imaging) and aid selection of the most appropriate imaging modality to facilitate breast examination in women who have undergone Macrolane breast enhancement.

  5. Radiological assessment of the breast following enhancement with Macrolane: Managing the challenges

    Energy Technology Data Exchange (ETDEWEB)

    Scaperrotta, Gianfranco, E-mail: gianfranco.scaperrotta@istitutotumori.mi.it [Fondazione IRCCS Istituto Nazionale dei Tumori, Via Venezian 1, 20133 Milan (Italy); Satchithananda, Keshtra, E-mail: keshthra.satchi@virgin.net [Imaging Department, King’s College Hospital NHS Foundation Trust and King’s College, Second Floor, Denmark Wing, Denmark Hill, London SE5 9RS (United Kingdom); Tengvar, Magnus, E-mail: magnus.tengvar@karolinska.se [Radiology Department, Karolinska University Hospital, Karolinska Vägen, 171 76 Solna (Sweden); Post, Karin, E-mail: karin.post@t-online.de [Radiologie Nuklearmedizin, Diakonissen KH, Speyerer Straße 91, 68163 Mannheim (Germany); Lim, Adrian K. [Imaging Department, Imperial College Healthcare NHS Trust, Charing Cross Hospital, Fulham Palace Road, London W6 8RF (United Kingdom); Panizza, Pietro, E-mail: ppanizza@sirm.org [Radiology Department, San Raffaele Hospital, Via Olgettina 60, 20132 Milan (Italy); Wesolowska, Ewa, E-mail: ewawu7@wp.pl [The M. Sklodowska-Curie Memorial Cancer Center and Institute of Oncology, 02-034 Warsaw, ul. Wawelska 15B (Poland); Inglefield, Christopher J., E-mail: chris@lbps.co.uk [London Bridge Plastic Surgery and Aesthetic Clinic, 54 Wimpole Street, London W1G 8YJ (United Kingdom)

    2017-01-15

    Highlights: • Macrolane VRF{sup ®}, a biodegradable, stabilized hyaluronic acid gel, was used for breast enhancement 2008–2012. • Even after more than 4 years, small amounts of Macrolane can still be visible on magnetic resonance imaging (MRI) or ultrasound in some patients similar to permanent implants, the presence of Macrolane gel may interfere with interpretation of mammography. • Knowledge of the product’s appearance on radiological assessment of breasts following Macrolane treatment is therefore required. • It is possible to assess the vast majority of patients using a combination of digital mammography and ultrasonography examination. - Abstract: Macrolane VRF{sup ®}, a biodegradable, stabilized hyaluronic acid gel, was used for breast enhancement 2008–2012. Similar to permanent implants, the presence of Macrolane gel may interfere with interpretation of mammography. This short communication aims to provide a guide to the appearance of Macrolane on radiology examination (including mammography, ultrasound and magnetic resonance imaging) and aid selection of the most appropriate imaging modality to facilitate breast examination in women who have undergone Macrolane breast enhancement.

  6. Natural radioactivity level and radiological hazard assessment of commonly used building material in Xining, China

    International Nuclear Information System (INIS)

    Shigang Chao; Xinwei Lu; Mengmeng Zhang; Long Pang

    2014-01-01

    Natural radioactivity of the commonly used building materials in Xining of China was measured using gamma-ray spectrometer system comprising a NaI(Tl) detector. Radioactivity concentrations of 226 Ra, 232 Th and 40 K in the studied samples range from 11.6 to 120.6, 10.2 to 107.1 and 228.0 to 1,036.2 Bq kg -1 , respectively. The concentrations for these natural radionuclides were compared with the reported data of other countries and the mean value for soil. Radium equivalent activity, indoor air absorbed dose rate, annual effective dose rate as well as external and internal hazard indices were calculated to assess radiological hazards for people living in dwelling made of the building materials. The radiological hazard assessment results show that the studied building materials, except for some aerated concrete block samples, are safe for use in construction of dwellings in the study area and do not pose any significant source of radiation hazard. (author)

  7. Data fusion for a vision-aided radiological detection system: Calibration algorithm performance

    Science.gov (United States)

    Stadnikia, Kelsey; Henderson, Kristofer; Martin, Allan; Riley, Phillip; Koppal, Sanjeev; Enqvist, Andreas

    2018-05-01

    In order to improve the ability to detect, locate, track and identify nuclear/radiological threats, the University of Florida nuclear detection community has teamed up with the 3D vision community to collaborate on a low cost data fusion system. The key is to develop an algorithm to fuse the data from multiple radiological and 3D vision sensors as one system. The system under development at the University of Florida is being assessed with various types of radiological detectors and widely available visual sensors. A series of experiments were devised utilizing two EJ-309 liquid organic scintillation detectors (one primary and one secondary), a Microsoft Kinect for Windows v2 sensor and a Velodyne HDL-32E High Definition LiDAR Sensor which is a highly sensitive vision sensor primarily used to generate data for self-driving cars. Each experiment consisted of 27 static measurements of a source arranged in a cube with three different distances in each dimension. The source used was Cf-252. The calibration algorithm developed is utilized to calibrate the relative 3D-location of the two different types of sensors without need to measure it by hand; thus, preventing operator manipulation and human errors. The algorithm can also account for the facility dependent deviation from ideal data fusion correlation. Use of the vision sensor to determine the location of a sensor would also limit the possible locations and it does not allow for room dependence (facility dependent deviation) to generate a detector pseudo-location to be used for data analysis later. Using manually measured source location data, our algorithm-predicted the offset detector location within an average of 20 cm calibration-difference to its actual location. Calibration-difference is the Euclidean distance from the algorithm predicted detector location to the measured detector location. The Kinect vision sensor data produced an average calibration-difference of 35 cm and the HDL-32E produced an average

  8. Novel real-time 3D radiological mapping solution for ALARA maximization, D and D assessments and radiological management

    Energy Technology Data Exchange (ETDEWEB)

    Dubart, Philippe; Hautot, Felix [AREVA Group, 1 route de la Noue, Gif sur Yvette (France); Morichi, Massimo; Abou-Khalil, Roger [AREVA Group, Tour AREVA-1, place Jean Millier, Paris (France)

    2015-07-01

    Good management of dismantling and decontamination (D and D) operations and activities is requiring safety, time saving and perfect radiological knowledge of the contaminated environment as well as optimization for personnel dose and minimization of waste volume. In the same time, Fukushima accident has imposed a stretch to the nuclear measurement operational approach requiring in such emergency situation: fast deployment and intervention, quick analysis and fast scenario definition. AREVA, as return of experience from his activities carried out at Fukushima and D and D sites has developed a novel multi-sensor solution as part of his D and D research, approach and method, a system with real-time 3D photo-realistic spatial radiation distribution cartography of contaminated premises. The system may be hand-held or mounted on a mobile device (robot, drone, e.g). In this paper, we will present our current development based on a SLAM technology (Simultaneous Localization And Mapping) and integrated sensors and detectors allowing simultaneous topographic and radiological (dose rate and/or spectroscopy) data acquisitions. This enabling technology permits 3D gamma activity cartography in real-time. (authors)

  9. Novel real-time 3D radiological mapping solution for ALARA maximization, D and D assessments and radiological management

    International Nuclear Information System (INIS)

    Dubart, Philippe; Hautot, Felix; Morichi, Massimo; Abou-Khalil, Roger

    2015-01-01

    Good management of dismantling and decontamination (D and D) operations and activities is requiring safety, time saving and perfect radiological knowledge of the contaminated environment as well as optimization for personnel dose and minimization of waste volume. In the same time, Fukushima accident has imposed a stretch to the nuclear measurement operational approach requiring in such emergency situation: fast deployment and intervention, quick analysis and fast scenario definition. AREVA, as return of experience from his activities carried out at Fukushima and D and D sites has developed a novel multi-sensor solution as part of his D and D research, approach and method, a system with real-time 3D photo-realistic spatial radiation distribution cartography of contaminated premises. The system may be hand-held or mounted on a mobile device (robot, drone, e.g). In this paper, we will present our current development based on a SLAM technology (Simultaneous Localization And Mapping) and integrated sensors and detectors allowing simultaneous topographic and radiological (dose rate and/or spectroscopy) data acquisitions. This enabling technology permits 3D gamma activity cartography in real-time. (authors)

  10. Salt site performance assessment activities

    International Nuclear Information System (INIS)

    Kircher, J.F.; Gupta, S.K.

    1983-01-01

    During this year the first selection of the tools (codes) for performance assessments of potential salt sites have been tentatively selected and documented; the emphasis has shifted from code development to applications. During this period prior to detailed characterization of a salt site, the focus is on bounding calculations, sensitivity and with the data available. The development and application of improved methods for sensitivity and uncertainty analysis is a focus for the coming years activities and the subject of a following paper in these proceedings. Although the assessments to date are preliminary and based on admittedly scant data, the results indicate that suitable salt sites can be identified and repository subsystems designed which will meet the established criteria for protecting the health and safety of the public. 36 references, 5 figures, 2 tables

  11. The DECADE performance assessment program

    International Nuclear Information System (INIS)

    Weber, B.V.; Ottinger, P.F.; Commisso, R.J.; Thompson, J.; Rowley, J.E.; Filios, P.; Babineau, M.A.

    1996-01-01

    Previous analyses of DECADE Module 1 experiments indicated significant current loss between the plasma opening switch (POS) and an electron-beam load. A program was initiated to diagnose and improve the power flow to assess the performance of a multi-module DECADE system. Power flow measurements between the POS and load indicate high vacuum flow, distributed current loss and azimuthal asymmetries. A decreased load impedance reduces the fraction of the load current flowing in vacuum. Improved plasma source symmetry reduces losses near the load for long conduction times. Increased POS impedance is required to significantly improve the power coupling to the load. (author). 6 figs., 9 refs

  12. The DECADE performance assessment program

    Energy Technology Data Exchange (ETDEWEB)

    Weber, B V; Ottinger, P F; Commisso, R J [Naval Research Lab., Washington, DC (United States). Plasma Physics Div.; Goyer, J R; Kortbawi, D [Physics International Co., Berkeley, CA (United States); Thompson, J [Maxwell Labs., San Diego, CA (United States); Rowley, J E; Filios, P [Defense Nuclear Agency, Alexandria, VA (United States); Babineau, M A [Sverdlup Technology, Tullahoma, TN (United States)

    1997-12-31

    Previous analyses of DECADE Module 1 experiments indicated significant current loss between the plasma opening switch (POS) and an electron-beam load. A program was initiated to diagnose and improve the power flow to assess the performance of a multi-module DECADE system. Power flow measurements between the POS and load indicate high vacuum flow, distributed current loss and azimuthal asymmetries. A decreased load impedance reduces the fraction of the load current flowing in vacuum. Improved plasma source symmetry reduces losses near the load for long conduction times. Increased POS impedance is required to significantly improve the power coupling to the load. (author). 6 figs., 9 refs.

  13. Performance assessment of coupled processes

    International Nuclear Information System (INIS)

    Pigford, T.H.

    1987-01-01

    The author considers all processes to be coupled. For example, a waste package heats the surrounding rock and its pore water, creating gradients in density and pressure that result in increased water flow. That process can be described as coupled, in that the flow is a consequence of heating. In a narrower sense, one speaks also of the more weakly coupled transport processes, expressed by the Onsager reciprocal relations, that state that a transport current, i.e., flux, of heat is accompanied by a small transport current of material, as evidenced in isotope separation by thermal diffusion, the Thompson effect in thermoelectricity, etc. This paper presents a performance assessment of coupled processes

  14. The establishment of computer codes for radiological assessment on LLW final disposal in Taiwan

    International Nuclear Information System (INIS)

    Yang, C.C.; Chen, H.T.; Shih, C.L.; Yeh, C.S.; Tsai, C.M.

    1988-01-01

    For final shallow land disposal of Low Level Waste (LLW) in Taiwan, an effort was initiated to establish the evaluation codes for the needs of environmental impact analysis. The objective of the computer code is to set up generic radiological standards for future evaluation on 10 CFR Part 61 Licensing Requirements for Land Disposal of Radioactive Wastes. In determining long-term influences resulting from radiological impacts of LLW at disposal sites there are at least three quantifiable impact measures selected for calculation: dose to members of the public (individual and population), occupational exposures and costs. The computer codes are from INTRUDE, INVERSI and INVERSW of NUREG-0782, OPTIONR and GRWATRR of NUREG-0945. They are both installed in FACOM-M200 and IBM PC/AT systems of Institute of Nuclear Energy Research (INER). The systematic analysis of the computer codes depends not only on the data bases supported by NUREG/CR-1759 - Data Base for Radioactive Waste Management, Volume 3, Impact Analysis Methodology Report but also the information collected from the different exposure scenarios and pathways. The sensitivity study is also performed to assure the long-term stability and security for needs of determining performance objectives

  15. The disposal of high level radioactive waste and the need for assessing the radiological impact

    International Nuclear Information System (INIS)

    Johansson, G.; Haegg, C.

    1990-01-01

    Different options for the disposal of high level radioactive waste are being considered in several different countries. When assessing the possible future impact of these disposal concepts, very large uncertainties are associated with the predictions. These uncertainties include scenario representation, conceptual and mathematical modelling, parameter evaluation and finally the interpretation of the results. Some of these uncertainties cannot be eliminated regardless of research efforts, e.g. the evolution of the society and the environment. The paper discusses in general terms to what extent uncertainties in the predictions could be reduced and in the light of this discussion the authors present their point of view regarding the fruitfulness of assessing radiological impact in the far future. (orig.)

  16. Delay times between harvesting or collection of food products and consumption for use in radiological assessments

    International Nuclear Information System (INIS)

    Jones, A L; Sherwood, J C

    2009-01-01

    From a radiological protection point of view, the inclusion of delay times when carrying out assessments of dose from consumption of foods should be considered. A review of delay times has been carried out to update a report published in 1983, to take account of changes and modernisations in industrial food processes, together with changes in diet and popularity of different foods in the United Kingdom. The new review considered more foods and data for existing foods have been reconsidered to check whether manufacturing processes or procedures have changed the shelf-life of any products. For some foods there have been changes made to the recommended delay times because of changes in manufacture or handling of the fresh foodstuff. A discussion is also included on the appropriate use of delay times in dose assessments.

  17. Assessment of the radiological impact of intermediate level waste disposed on the seabed

    International Nuclear Information System (INIS)

    Mobbs, S.F.; Hill, M.D.

    1982-12-01

    This report outlines the methodology to be used in radiological assessments of disposal of waste on the ocean bed and describes the set of integrated models needed for such assessments. During the period covered by the contract considerable progress was made towards developing a new, compartment-type, model for dispersion of radionuclides in the deep ocean. The basic structure of this model was defined, and the mathematical techniques to be used in calculating the water flow rates between compartments were identified. Calculations of these flow rates are about to begin. When further progress has been made on the deep ocean model, more effort will be devoted to the other two models which are seen to be of high priority. These are the waste package model and the sedimentation model. It is anticipated that a first set of integrated models will be available for use in 1983, and will be refined thereafter. (author)

  18. 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

  19. Comparison of patient doses in interventional radiology procedures performed in two large hospitals in Greece

    International Nuclear Information System (INIS)

    Papageorgiou, E.; Tsapaki, V.; Tsalafoutas, I. A.; Maurikou, E.; Kottou, S.; Orfanos, A.; Karidas, G.; Fidanis, T.; Zafiriadou, E.; Neofotistou, V.

    2007-01-01

    Purpose of the study was to determine patient doses in the most common interventional radiology (IR) procedures performed in two large Greek hospitals. A total of 164 patients who underwent 4 types of IR procedures were studied. Fluoroscopy time, total exposure time, number of frames, number of runs, radiation field size, and cumulative dose-area product (DAP) were recorded. The median DAP values for carotid arteriography and lower limb arteriography were 66 and 123 Gy cm 2 for hospital 'A' and 21 and 49 Gy cm 2 for hospital 'B'. For the cerebral arteriographies performed in hospital 'A', the median DAP was 116 Gy cm 2 while for the hepatic embolizations performed in hospital 'B', it was 104 Gy cm 2 . The DAP values observed in hospital 'A' for carotid arteriography and lower limb arteriography were almost three times than those of hospital 'B'. From the data analysis, it is evident that dose optimization in hospital 'A' should be pursued through revision of the techniques used. (authors)

  20. Determining the Suitability of Materials for Disposal at Sea under the London Convention 1972 and London Protocol 1996: A Radiological Assessment Procedure. 2015 Edition

    International Nuclear Information System (INIS)

    2015-01-01

    This publication provides guidance on performing specific assessments of candidate materials for dumping at sea, to determine whether the materials are de minimis in the meaning of the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter 1972 (the London Convention 1972) and the related Protocol 1996 (the London Protocol 1996). It presents a detailed radiological procedure to assess doses to workers and members of the public and doses to marine flora and fauna related to the dumping of materials at sea. The procedures in this publication follow the requirements to protect the environment in the IAEA Safety Standards and in the recommendations by the International Commission of Radiological Protection. It is expected to be used by national regulatory authorities responsible for authorizing disposal at sea of candidate materials as well as by those companies and individuals applying to obtain permission to dispose these materials at sea

  1. Radiological impact assessment to the environment due to waste from disposal of porcelain.

    Science.gov (United States)

    Morsi, Tarek; Hegazy, Rehab; Badawy, Wael

    2017-06-01

    The present study aimed to assess the radiological parameters from gamma rays due to the uncontrolled disposal of porcelain waste to the environment. Qualitative and quantitative identification of radionuclides in the investigated samples was carried out by means of a high-purity germanium (HPGe) detector. The average activity concentrations of the local porcelain samples were measured as 208.28 Bq/kg for 226 Ra, 125.73 Bq/kg for 238 U, 84.94 Bq/kg for 232 Th and 1033.61 Bq/kg for 40 K, respectively. The imported samples had an average activity of 240.57 Bq/kg for 226 Ra, 135.56 Bq/kg for 238 U, 115.74 Bq/kg for 232 Th and 1312.49 Bq/kg for 40 K, respectively. Radiological parameters and the radium equivalent Ra eq for the investigated samples were calculated. The external and internal hazard indices, representative level index (I γ ), alpha index (I α ), and the exemption level (I x ), were estimated to be higher than the recommended value (unity), while the average activity concentrations for the studied samples were higher than recommended levels. In conclusion, we are concerned that disposal of porcelain in the environment might be a significant hazard.

  2. Radiological assessment of surface water quality around proposed uranium mining site in India.

    Science.gov (United States)

    Jha, S K; Lenka, P; Gothankar, S; Tripathi, R M; Puranik, V D; Khating, D T

    2009-06-01

    The gross alpha and gross beta activities were estimated for radiological assessment of surface water quality around the proposed uranium mining site Kylleng Pyndengsohiong Mawthabah (Domiasiat), West Khasi Hills District, Meghalaya situated in a high rainfall area (12,000mm) in India. 189 Surface water samples were collected over different seasons of the year from nine different locations covering around 100km(2). Gross beta activities were found to vary from 144 to 361mBq/L which is much below the prescribed WHO limit of 1000mBq/L for drinking water. Gross alpha activities varied from 61 to 127mBq/L. These values are much below the reported gross alpha values by other countries. In about 7% of the samples the alpha activities remain exceeded the WHO guideline limit of 100mBq/L. Surface water samples collected during the summer season of the year show higher activity whereas low activity was found from samples collected during monsoon season. Results show that all water sources are acceptable as drinking water for human consumption from the radiological point of view, the higher gross alpha concentrations in a few locations remains so only for short duration during the summer season.

  3. Radiological assessment of surface water quality around proposed uranium mining site in India

    International Nuclear Information System (INIS)

    Jha, S.K.; Lenka, P.; Gothankar, S.; Tripathi, R.M.; Puranik, V.D.; Khating, D.T.

    2009-01-01

    The gross alpha and gross beta activities were estimated for radiological assessment of surface water quality around the proposed uranium mining site Kylleng Pyndengsohiong Mawthabah (Domiasiat), West Khasi Hills District, Meghalaya situated in a high rainfall area (12,000 mm) in India. 189 Surface water samples were collected over different seasons of the year from nine different locations covering around 100 km 2 . Gross beta activities were found to vary from 144 to 361 mBq/L which is much below the prescribed WHO limit of 1000 mBq/L for drinking water. Gross alpha activities varied from 61 to 127 mBq/L. These values are much below the reported gross alpha values by other countries. In about 7% of the samples the alpha activities remain exceeded the WHO guideline limit of 100 mBq/L. Surface water samples collected during the summer season of the year show higher activity whereas low activity was found from samples collected during monsoon season. Results show that all water sources are acceptable as drinking water for human consumption from the radiological point of view, the higher gross alpha concentrations in a few locations remains so only for short duration during the summer season.

  4. Assessment of the radiological status of the French environment between June 2011 and December 2014

    International Nuclear Information System (INIS)

    Renaud, Philippe; Bruno, Valerie; Caldeira Ideias, Pedro; Calmon, Philippe; Claval, David; Couvez, Celine; D'Amico, Donato; Debayle, Christophe; Leprieur, Fabrice; Masson, Olivier; Pierrard, Olivier; Pourcelot, Laurent; Roussel-Debet, Sylvie; Renaud, Philippe; Saey, Lionel; Tournieux, Damien; Delabbaye, Pascale; Manificat, Guillaume

    2016-01-01

    This huge report first proposes a presentation of the radiological control of the environment in France: its objectives, its various tools (for the control of the atmosphere, of waters, of soils), its sampling plan and its measurement results, and the national network for measurements of radioactivity of the environment (RNM) with its members, agreements and information system. The second part addresses the French radiological background noise, i.e. the natural sources of radiation and exposure (telluric and cosmogenic radionuclides), exposure doses (from the air, by ingestion by food and smoking, by radon inhalation), and the persistence of old radioactive fallouts and associated exposures. The third part presents data related to different French nuclear sites: operated electronuclear plants (releases, plan of control of the environment, influence of these sites on their environment and associated public exposures), to electronuclear plants being currently dismantled, to industrial sites, to research centres, to nuclear naval bases, and to ancient mining sites. A synthesis of dose assessment is finally proposed. The next part describes radioactivity and resulting exposures of people (radionuclides, radiations, activity measurement expressed in Becquerel, radioactive period, exposure modes, dose expressed in Sievert, and aspects related to radiation protection). The last part presents various sources of information on the control of radioactivity and data diffusion: internet sites and public information supports, information diffusion based on international treaties and conventions

  5. Assessment of radiological environment around coal mining area of Dhanbad, Jharkhand

    International Nuclear Information System (INIS)

    Patnaik, R.L.; Thakur, V.K.; Jha, V.N.; Sethy, N.K.; Srivastava, V.S.; Kumar, Rajesh; Tripathi, R.M.; Puranik, V.D.

    2012-01-01

    Naturally occurring radionuclides present in the earth crust is a significant source of human exposure. Variation in natural background radiation is expected in different geological formations. Anthropogenic activities in geological formation of elevated radionuclide level may enhance the area background. In areas of coal mining industries investigation of radiological environment is required as the residues contains significant amount of uranium and thorium series radionuclides (Van Hook, 1 979, Balogun, 2003). Radon and its short-lived progeny present in the environment contributes maximum natural background radiation dose due to inhalation. Apart from this radionuclide content in key environmental matrices may also contribute to inhalation and ingestion exposure for members of public. Present investigation was carried out in coal mining areas of Dhanbad, Jharkhand to assess the existing radiological status. A detailed investigation is required to evaluate the environmental impact of coal handling activities in the area. The contribution of 222 Rn progeny towards outdoor inhalation dose compares with global average reported by UNSCEAR (2006)

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

    International Nuclear Information System (INIS)

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

    1991-12-01

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

  7. Assessment of Musculoskeletal Function and its Correlation with Radiological Joint Score in Children with Hemophilia A.

    Science.gov (United States)

    Gupta, Samriti; Garg, Kapil; Singh, Jagdish

    2015-12-01

    To evaluate the functional independence of children with hemophilia A and its correlation to radiological joint score. The present cross sectional study was conducted at SPMCHI, SMS Medical College, Jaipur, India. Children in the age group of 4-18 y affected with severe, moderate and mild hemophilia A and with a history of hemarthrosis who attended the OPD, emergency or got admitted in wards of SPMCHI, SMS Medical College were examined. Musculoskeletal function was measured in 98 patients using Functional Independence Score in Hemophilia (FISH) and index joints (joints most commonly affected with repeated bleeding) were assessed radiologically with plain X rays using Pettersson score. The mean FISH score was 28.07 ± 3.90 (range 17-32) with squatting, running and step climbing as most affected tasks. The mean Pettersson score was 3.8 ± 3.2. A significant correlation was found between mean Pettersson score and FISH (r = -0.875, P hemophilia A.

  8. 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

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

    International Nuclear Information System (INIS)

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

    1991-11-01

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

  10. 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.

  11. Designing Second Language Performance Assessments. Technical Report.

    Science.gov (United States)

    Norris, John M.; Brown, James Dean; Hudson, Thom; Yoshioka, Jim

    This technical report focuses on the decision-making potential provided by second language performance assessments. First, performance assessment is situated within the broader discussion of alternatives in language assessment and in educational assessment in general. Next, issues in performance assessment design, implementation, reliability, and…

  12. The development of a postal method to assess X-ray beam parameters and image quality in dental radiology

    International Nuclear Information System (INIS)

    Fenton, D.M.

    1994-10-01

    Intraoral radiographs are an extremely valuable diagnostic tool in dentistry. Radiography permits the early detection and diagnosis of dental disease and consequently is used extensively. However, public concern about radiation exposure has increased in recent times. This concern is reflected in national and international law, to the extent that, the basic principles of radiological protection, that is, justification, optimisation and dose limitation are written into law. Furthermore, in Ireland, the regulations, as outlined in the Code of Practice for Radiological Protection in Dentistry, require intraoral dental X-ray machines to perform to certain standards. A report of a direct survey of 164 intraoral dental X-ray machines is given in this study. The survey covered mechanical, electrical as well as radiation safety. Inadequacies with respect to focus to skin distance and timer accuracy were found in 45% and 42% of the machines surveyed. Ninety eight machines were assessed for electrical safety in which 48% were found to be unsafe. The results indicate that a complete assessment of the performance of dental X-ray units in Ireland is required. However, as there are in excess of 800 dental X-ray machines located throughout the country, such an assessment would be very costly for the regulatory authority. The development of a postal method for the assessment of the performance of dental X-ray machines is described in this study. This postal method provides information on the kV, total filtration, beam width and timer linearity and is undertaken by means of a penetrameter and film envelopes for exposure to the X-ray set under examination, together with a questionnaire that requests information on environment in which the machine is located. Using this method an accuracy of +-5% of the actual value was achieved in the measurement of kVp. The penetrameter was also used to assess whether or not the filtration of a particular machine complies with the regulations. This

  13. Quality assurance in performance assessments

    International Nuclear Information System (INIS)

    Maul, P.R.; Watkins, B.M.; Salter, P.; Mcleod, R

    1999-01-01

    Following publication of the Site-94 report, SKI wishes to review how Quality Assurance (QA) issues could be treated in future work both in undertaking their own Performance Assessment (PA) calculations and in scrutinising documents supplied by SKB (on planning a repository for spent fuels in Sweden). The aim of this report is to identify the key QA issues and to outline the nature and content of a QA plan which would be suitable for SKI, bearing in mind the requirements and recommendations of relevant standards. Emphasis is on issues which are specific to Performance Assessments for deep repositories for radioactive wastes, but consideration is also given to issues which need to be addressed in all large projects. Given the long time over which the performance of a deep repository system must be evaluated, the demonstration that a repository is likely to perform satisfactorily relies on the use of computer-generated model predictions of system performance. This raises particular QA issues which are generally not encountered in other technical areas (for instance, power station operations). The traceability of the arguments used is a key QA issue, as are conceptual model uncertainty, and code verification and validation; these were all included in the consideration of overall uncertainties in the Site-94 project. Additionally, issues which are particularly relevant to SKI include: How QA in a PA fits in with the general QA procedures of the organisation undertaking the work. The relationship between QA as applied by the regulator and the implementor of a repository development programme. Section 2 introduces the discussion of these issues by reviewing the standards and guidance which are available from national and international organisations. This is followed in Section 3 by a review of specific issues which arise from the Site-94 exercise. An outline procedure for managing QA issues in SKI is put forward as a basis for discussion in Section 4. It is hoped that

  14. Quality assurance in performance assessments

    Energy Technology Data Exchange (ETDEWEB)

    Maul, P.R.; Watkins, B.M.; Salter, P.; Mcleod, R [QuantiSci Ltd, Henley-on-Thames (United Kingdom)

    1999-01-01

    Following publication of the Site-94 report, SKI wishes to review how Quality Assurance (QA) issues could be treated in future work both in undertaking their own Performance Assessment (PA) calculations and in scrutinising documents supplied by SKB (on planning a repository for spent fuels in Sweden). The aim of this report is to identify the key QA issues and to outline the nature and content of a QA plan which would be suitable for SKI, bearing in mind the requirements and recommendations of relevant standards. Emphasis is on issues which are specific to Performance Assessments for deep repositories for radioactive wastes, but consideration is also given to issues which need to be addressed in all large projects. Given the long time over which the performance of a deep repository system must be evaluated, the demonstration that a repository is likely to perform satisfactorily relies on the use of computer-generated model predictions of system performance. This raises particular QA issues which are generally not encountered in other technical areas (for instance, power station operations). The traceability of the arguments used is a key QA issue, as are conceptual model uncertainty, and code verification and validation; these were all included in the consideration of overall uncertainties in the Site-94 project. Additionally, issues which are particularly relevant to SKI include: How QA in a PA fits in with the general QA procedures of the organisation undertaking the work. The relationship between QA as applied by the regulator and the implementor of a repository development programme. Section 2 introduces the discussion of these issues by reviewing the standards and guidance which are available from national and international organisations. This is followed in Section 3 by a review of specific issues which arise from the Site-94 exercise. An outline procedure for managing QA issues in SKI is put forward as a basis for discussion in Section 4. It is hoped that

  15. Radiological assessment of the Rhone valley. Final report related to the ground environment

    International Nuclear Information System (INIS)

    Roussel-Debet, S.; Saey, L.; Mourier, D.; Salaun, G.

    2012-01-01

    This report presents and comments the results obtained during a ground radiological survey performed in the Rhone valley from May 2009 to end of 2011. It recalls the general sampling and analysis strategy, in terms of objectives, locations, samples to measure tritium and carbon 14, and specific samples. It presents and discusses results obtained for tritium and carbon 14, and notably measurements obtained in boar meat. Other commented results are those obtained by gamma spectrometry on farm products (measurements of natural and artificial radionuclides), by analysis of milk products, and by specific samplings and analysis (bio-indicators in the vicinity of Marcoule, Camargue sands and beaches, rice field grounds, measurements performed after the Fukushima accident)

  16. How Visual Search Relates to Visual Diagnostic Performance: A Narrative Systematic Review of Eye-Tracking Research in Radiology

    Science.gov (United States)

    van der Gijp, A.; Ravesloot, C. J.; Jarodzka, H.; van der Schaaf, M. F.; van der Schaaf, I. C.; van Schaik, J. P.; ten Cate, Th. J.

    2017-01-01

    Eye tracking research has been conducted for decades to gain understanding of visual diagnosis such as in radiology. For educational purposes, it is important to identify visual search patterns that are related to high perceptual performance and to identify effective teaching strategies. This review of eye-tracking literature in the radiology…

  17. How visual search relates to visual diagnostic performance : a narrative systematic review of eye-tracking research in radiology

    NARCIS (Netherlands)

    van der Gijp, A; Ravesloot, C J; Jarodzka, H; van der Schaaf, M F; van der Schaaf, I C; van Schaik, J P J; ten Cate, Olle

    Eye tracking research has been conducted for decades to gain understanding of visual diagnosis such as in radiology. For educational purposes, it is important to identify visual search patterns that are related to high perceptual performance and to identify effective teaching strategies. This review

  18. Communicating Performance Assessments Results - 13609

    International Nuclear Information System (INIS)

    Layton, Mark

    2013-01-01

    The F-Area Tank Farms (FTF) and H-Area Tank Farm (HTF) are owned by the U.S. Department of Energy (DOE) and operated by Savannah River Remediation LLC (SRR), Liquid Waste Operations contractor at DOE's Savannah River Site (SRS). The FTF and HTF are active radioactive waste storage and treatment facilities consisting of 51 carbon steel waste tanks and ancillary equipment such as transfer lines, evaporators and pump tanks. Performance Assessments (PAs) for each Tank Farm have been prepared to support the eventual closure of the underground radioactive waste tanks and ancillary equipment. PAs provide the technical bases and results to be used in subsequent documents to demonstrate compliance with the pertinent requirements for final closure of the Tank Farms. The Tank Farms are subject to a number of regulatory requirements. The State regulates Tank Farm operations through an industrial waste water permit and through a Federal Facility Agreement approved by the State, DOE and the Environmental Protection Agency (EPA). Closure documentation will include State-approved Tank Farm Closure Plans and tank-specific closure modules utilizing information from the PAs. For this reason, the State of South Carolina and the EPA must be involved in the performance assessment review process. The residual material remaining after tank cleaning is also subject to reclassification prior to closure via a waste determination pursuant to Section 3116 of the Ronald W. Reagan National Defense Authorization Act of Fiscal Year 2005. PAs are performance-based, risk-informed analyses of the fate and transport of FTF and HTF residual wastes following final closure of the Tank Farms. Since the PAs serve as the primary risk assessment tools in evaluating readiness for closure, it is vital that PA conclusions be communicated effectively. In the course of developing the FTF and HTF PAs, several lessons learned have emerged regarding communicating PA results. When communicating PA results it is

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

    International Nuclear Information System (INIS)

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

    2011-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-07-01

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

  1. Improved power performance assessment methods

    Energy Technology Data Exchange (ETDEWEB)

    Frandsen, S; Antoniou, I; Dahlberg, J A [and others

    1999-03-01

    The uncertainty of presently-used methods for retrospective assessment of the productive capacity of wind farms is unacceptably large. The possibilities of improving the accuracy have been investigated and are reported. A method is presented that includes an extended power curve and site calibration. In addition, blockage effects with respect to reference wind speed measurements are analysed. It is found that significant accuracy improvements are possible by the introduction of more input variables such as turbulence and wind shear, in addition to mean wind speed and air density. Also, the testing of several or all machines in the wind farm - instead of only one or two - may provide a better estimate of the average performance. (au)

  2. 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

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

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  4. Assessment of the radiological impact of disposal of low and intermediate level wastes on the seabed

    International Nuclear Information System (INIS)

    Mobbs, S.F.; Delow, C.E.; Hill, M.D.

    1984-03-01

    This report describes progress in the development of models for use in a radiological assessment of the disposal of low and intermediate level waste on the ocean floor. In particular the report describes the waste package model, the ocean dispersion model and the sedimentation model. Five types of waste package have been identified and models have been developed for them. A flow pattern for the Atlantic Ocean has been derived from the existing distribution of temperature and salinity in the Atlantic Ocean. However a number of discrepancies between the calculated and predicted pattern were found; the model has been extended to include all the world's oceans to correct this. The sedimentation model describes two types of scavenging particles in the water column, a well mixed benthic boundary layer and the top two metres of the bed sediments. Good agreement with the GESAMP ocean model results has been found. (author)

  5. Radiological assessment of private water supplies in the Borough of Beverley, East Yorkshire, England

    International Nuclear Information System (INIS)

    1992-01-01

    Water samples from 100 private water supplies in the Borough of Beverley have been analysed for natural and artificial radionuclides and the elements Calcium and Strontium. In addition, 20 of the 100 supplies were specifically sampled for the measurement of Radon-222. Of the 100 supplies tested, all total alpha and beta analyses were within the WHO guideline values. An assessment of the radiological significance of the analytical data has been carried out by calculating the committed effective dose equivalent to a hypothetical ''critical'' group, which would arise from the consumption of water during a single year. The maximum adult annual committed effective dose equivalent for artificial and total radionuclides measured during this programme of monitoring was found to be 1.50 and 20.9 μSv, respectively. (author)

  6. Radiological assessment of private water supplies in Berwick-upon-Tweed, England

    International Nuclear Information System (INIS)

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

    1993-01-01

    Water samples from 95 private water supplies and 5 main supplies in the Berwick-Upon-Tweed area of England have been analysed for natural and artificial radionuclides and the elements Calcium and Strontium. In addition 20 of the 100 supplies were specifically sampled for the measurement of Radon-222. Of the 100 supplies tested, all total alpha and beta values were within the WHO guideline values. An assessment of the radiological significance of the analytical data has been carried out by calculating the committed effective dose equivalent to a hypothetical ''Critical'' group which would arise from the consumption of water during a single year. The maximum infant annual committed effective dose equivalent for artificial and total radionuclides measured during this programme of monitoring was found to be 0.5 μSv and 2290μSv respectively. (Author)

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

    International Nuclear Information System (INIS)

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

    1992-01-01

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

  8. 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

  9. An Assessment of Radiologically Inserted Transoral and Transgastric Gastroduodenal Stents to Treat Malignant Gastric Outlet Obstruction

    Energy Technology Data Exchange (ETDEWEB)

    Miller, Bethany H. T., E-mail: bmiller@doctors.org.uk [Lancashire Teaching Hospitals NHS Foundation Trust, Royal Preston Hospital, Department of Upper Gastrointestinal Surgery (United Kingdom); Griffiths, Ewen A., E-mail: Eagriffiths@doctors.org.uk [The New Queen Elizabeth Hospital, Department of Upper Gastrointestinal Surgery (United Kingdom); Pursnani, Kishore G., E-mail: Kish.Pursnani@lthtr.nhs.uk; Ward, Jeremy B., E-mail: Jeremy.Ward@lthtr.nhs.uk [Lancashire Teaching Hospitals NHS Foundation Trust, Royal Preston Hospital, Department of Upper Gastrointestinal Surgery (United Kingdom); Stockwell, Robert C., E-mail: Robert.Stockwell@lthtr.nhs.uk [Lancashire Teaching Hospitals NHS Foundation Trust, Chorley and South Ribble Hospital, Department of Radiology (United Kingdom)

    2013-12-15

    IntroductionSelf-expanding metallic stents (SEMS) are used to palliate malignant gastric outlet obstruction (GOO) and are useful in patients with limited life expectancy or severe medical comorbidity, which would preclude surgery. Stenting can be performed transorally or by a percutaneous transgastric technique. Our goal was to review the outcome of patients who underwent radiological SEMS insertion performed by a single consultant interventional radiologist. Methods: Patients were identified from a prospectively collected database held by one consultant radiologist. Data were retrieved from radiological reports, multidisciplinary team meetings, and the patients' case notes. Univariate survival analysis was performed. Results: Between December 2000 and January 2011, 100 patients (63 males, 37 females) had 110 gastroduodenal stenting procedures. Median age was 73 (range 39-89) years. SEMS were inserted transorally (n = 66) or transgastrically (n = 44). Site of obstruction was the stomach (n = 37), duodenum (n = 50), gastric pull-up (n = 10), or gastroenterostomy (n = 13). Seven patients required biliary stents. Technical success was 86.4 %: 83.3 % for transoral insertion, 90.9 % for transgastric insertion. Eleven patients developed complications. Median GOO severity score: 1 pre-stenting, 2 post-stenting (p = 0.0001). Median survival was 54 (range 1-624) days. Post-stenting GOO severity score was predictive of survival (p = 0.0001). Conclusions: The technical success rate for insertion of palliative SEMS is high. Insertional technique can be tailored to the individual depending on the location of the tumor and whether it is possible to access the stomach percutaneously. Patients who have successful stenting and return to eating a soft/normal diet have a statistically significant increase in survival.

  10. An Assessment of Radiologically Inserted Transoral and Transgastric Gastroduodenal Stents to Treat Malignant Gastric Outlet Obstruction

    International Nuclear Information System (INIS)

    Miller, Bethany H. T.; Griffiths, Ewen A.; Pursnani, Kishore G.; Ward, Jeremy B.; Stockwell, Robert C.

    2013-01-01

    IntroductionSelf-expanding metallic stents (SEMS) are used to palliate malignant gastric outlet obstruction (GOO) and are useful in patients with limited life expectancy or severe medical comorbidity, which would preclude surgery. Stenting can be performed transorally or by a percutaneous transgastric technique. Our goal was to review the outcome of patients who underwent radiological SEMS insertion performed by a single consultant interventional radiologist. Methods: Patients were identified from a prospectively collected database held by one consultant radiologist. Data were retrieved from radiological reports, multidisciplinary team meetings, and the patients’ case notes. Univariate survival analysis was performed. Results: Between December 2000 and January 2011, 100 patients (63 males, 37 females) had 110 gastroduodenal stenting procedures. Median age was 73 (range 39–89) years. SEMS were inserted transorally (n = 66) or transgastrically (n = 44). Site of obstruction was the stomach (n = 37), duodenum (n = 50), gastric pull-up (n = 10), or gastroenterostomy (n = 13). Seven patients required biliary stents. Technical success was 86.4 %: 83.3 % for transoral insertion, 90.9 % for transgastric insertion. Eleven patients developed complications. Median GOO severity score: 1 pre-stenting, 2 post-stenting (p = 0.0001). Median survival was 54 (range 1–624) days. Post-stenting GOO severity score was predictive of survival (p = 0.0001). Conclusions: The technical success rate for insertion of palliative SEMS is high. Insertional technique can be tailored to the individual depending on the location of the tumor and whether it is possible to access the stomach percutaneously. Patients who have successful stenting and return to eating a soft/normal diet have a statistically significant increase in survival

  11. 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

  12. The development of a surface hydrology model for use in radiological safety assessments

    International Nuclear Information System (INIS)

    Little, R.H.; Ashton, J.

    1991-01-01

    A detailed understanding and quantification of geosphere and biosphere water movements is vital when assessing the impact of a radioactive waste repository. Not only is water important in the transport of radionuclides from the repository into the geosphere and hence into the biosphere, but it is also important in the transport of radionuclides within the biosphere and their transport to humans. Although geosphere water fluxes have traditionally been rigorously quantified, the quantification of biosphere water fluxes has been far less rigorous. In order to redress the balance, Associated Nuclear Services Ltd (ANS) have proposed to develop a surface hydrology model for use within radiological assessments undertaken by Her Majesty's Inspectorate of Pollution (HMIP) of the United Kingdom Department of the Environment (UKDoE). It is proposed that the deterministic, lumped, quasi-physical/semi-empirical approach of conceptual models should be adopted for the model. The model will be sufficiently flexible to be applicable to a wide range of catchments, as well as a variety of temporal and spatial scales. It is envisaged that the model will have a variety of uses within the HMIP assessment methodology including the identification of significant surface hydrological processes, the provision of input data for assessment codes and the study of the biosphere-geosphere interface. (17 refs., 4 figs.)

  13. 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

  14. Communicating Performance Assessments Results - 13609

    Energy Technology Data Exchange (ETDEWEB)

    Layton, Mark [Savannah River Remediation LLC, Building 705-1C, Aiken, SC 29808 (United States)

    2013-07-01

    The F-Area Tank Farms (FTF) and H-Area Tank Farm (HTF) are owned by the U.S. Department of Energy (DOE) and operated by Savannah River Remediation LLC (SRR), Liquid Waste Operations contractor at DOE's Savannah River Site (SRS). The FTF and HTF are active radioactive waste storage and treatment facilities consisting of 51 carbon steel waste tanks and ancillary equipment such as transfer lines, evaporators and pump tanks. Performance Assessments (PAs) for each Tank Farm have been prepared to support the eventual closure of the underground radioactive waste tanks and ancillary equipment. PAs provide the technical bases and results to be used in subsequent documents to demonstrate compliance with the pertinent requirements for final closure of the Tank Farms. The Tank Farms are subject to a number of regulatory requirements. The State regulates Tank Farm operations through an industrial waste water permit and through a Federal Facility Agreement approved by the State, DOE and the Environmental Protection Agency (EPA). Closure documentation will include State-approved Tank Farm Closure Plans and tank-specific closure modules utilizing information from the PAs. For this reason, the State of South Carolina and the EPA must be involved in the performance assessment review process. The residual material remaining after tank cleaning is also subject to reclassification prior to closure via a waste determination pursuant to Section 3116 of the Ronald W. Reagan National Defense Authorization Act of Fiscal Year 2005. PAs are performance-based, risk-informed analyses of the fate and transport of FTF and HTF residual wastes following final closure of the Tank Farms. Since the PAs serve as the primary risk assessment tools in evaluating readiness for closure, it is vital that PA conclusions be communicated effectively. In the course of developing the FTF and HTF PAs, several lessons learned have emerged regarding communicating PA results. When communicating PA results it is

  15. Radiological Assessment Survey of the Vance road Facility Source Vault Building Materials, Oak Ridge Institute for Science and Education, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Morton, J. R.

    2000-01-01

    From the 1950s, the Vance Road laboratory was the site of extensive nuclear medical research and involved the used of numerous radionuclides. These nuclides were stored in a source vault stored on the first floor of the facility. Nuclear medical research is no longer conducted in this facility, and the source vault was remediated in preparation for converting the area to office space and general use. The Environmental Survey and Site Assessment Program (ESSAP) of ORISE performed a radiological assessment survey of the source vault and its associated miscellaneous building materials and laboratory equipment in preparation for the conversion to general use space

  16. Behavior model for performance assessment

    International Nuclear Information System (INIS)

    Brown-VanHoozer, S. A.

    1999-01-01

    Every individual channels information differently based on their preference of the sensory modality or representational system (visual auditory or kinesthetic) we tend to favor most (our primary representational system (PRS)). Therefore, some of us access and store our information primarily visually first, some auditorily, and others kinesthetically (through feel and touch); which in turn establishes our information processing patterns and strategies and external to internal (and subsequently vice versa) experiential language representation. Because of the different ways we channel our information, each of us will respond differently to a task--the way we gather and process the external information (input), our response time (process), and the outcome (behavior). Traditional human models of decision making and response time focus on perception, cognitive and motor systems stimulated and influenced by the three sensory modalities, visual, auditory and kinesthetic. For us, these are the building blocks to knowing how someone is thinking. Being aware of what is taking place and how to ask questions is essential in assessing performance toward reducing human errors. Existing models give predications based on time values or response times for a particular event, and may be summed and averaged for a generalization of behavior(s). However, by our not establishing a basic understanding of the foundation of how the behavior was predicated through a decision making strategy process, predicative models are overall inefficient in their analysis of the means by which behavior was generated. What is seen is the end result

  17. Behavior model for performance assessment.

    Energy Technology Data Exchange (ETDEWEB)

    Borwn-VanHoozer, S. A.

    1999-07-23

    Every individual channels information differently based on their preference of the sensory modality or representational system (visual auditory or kinesthetic) we tend to favor most (our primary representational system (PRS)). Therefore, some of us access and store our information primarily visually first, some auditorily, and others kinesthetically (through feel and touch); which in turn establishes our information processing patterns and strategies and external to internal (and subsequently vice versa) experiential language representation. Because of the different ways we channel our information, each of us will respond differently to a task--the way we gather and process the external information (input), our response time (process), and the outcome (behavior). Traditional human models of decision making and response time focus on perception, cognitive and motor systems stimulated and influenced by the three sensory modalities, visual, auditory and kinesthetic. For us, these are the building blocks to knowing how someone is thinking. Being aware of what is taking place and how to ask questions is essential in assessing performance toward reducing human errors. Existing models give predications based on time values or response times for a particular event, and may be summed and averaged for a generalization of behavior(s). However, by our not establishing a basic understanding of the foundation of how the behavior was predicated through a decision making strategy process, predicative models are overall inefficient in their analysis of the means by which behavior was generated. What is seen is the end result.

  18. 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...

  19. Initial assessment of a model relating intratumoral genetic heterogeneity to radiological morphology

    Science.gov (United States)

    Noterdaeme, O; Kelly, M; Friend, P; Soonowalla, Z; Steers, G; Brady, M

    2010-01-01

    Tumour heterogeneity has major implications for tumour development and response to therapy. Tumour heterogeneity results from mutations in the genes responsible for mismatch repair or maintenance of chromosomal stability. Cells with different genetic properties may grow at different rates and exhibit different resistance to therapeutic interventions. To date, there exists no approach to non-invasively assess tumour heterogeneity. Here we present a biologically inspired model of tumour growth, which relates intratumoral genetic heterogeneity to gross morphology visible on radiological images. The model represents the development of a tumour as a set of expanding spheres, each sphere representing a distinct clonal centre, with the sprouting of new spheres corresponding to new clonal centres. Each clonal centre may possess different characteristics relating to genetic composition, growth rate and response to treatment. We present a clinical example for which the model accurately tracks tumour growth and shows the correspondence to genetic variation (as determined by array comparative genomic hybridisation). One clinical implication of our work is that the assessment of heterogeneous tumours using Response Evaluation Criteria In Solid Tumours (RECIST) or volume measurements may not accurately reflect tumour growth, stability or the response to treatment. We believe that this is the first model linking the macro-scale appearance of tumours to their genetic composition. We anticipate that our model will provide a more informative way to assess the response of heterogeneous tumours to treatment, which is of increasing importance with the development of novel targeted anti-cancer treatments. PMID:19690073

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

    Science.gov (United States)

    van Dillen, Teun; van Dijk, Arjan

    2018-06-12

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

  1. Radiological assessments for resettlement of Rongelap in the Republic of the Marshall Islands

    International Nuclear Information System (INIS)

    1994-01-01

    The Committee on Radiological Safety in the Marshall Islands was established by the National Research Council in response to a request from the US Department of Energy (DOE) to assist the department in evaluating radiological conditions on certain atolls in the Republic of the Marshall Islands, especially Rongelap Atoll. The need stems from the provisions of a memorandum of understanding (MOU) established between the Republic of the Marshall Islands and the US in 1992. That agreement sets out criteria and stipulations pertaining to the resettlement of Rongelap Atoll. The issue of resettlement itself originated in the desire for the people of the Marshall Islands to return to the atolls from which they were evacuated as a consequence of nuclear-weapons testing by the US during the 1940s and 1950s. The National Research Council was asked to review the scientific studies undertaken by the US Department of Energy to determine if reliable and modern scientific methodology was being used to assess the potential hazard, if any, to persons who might return to live on Rongelap Atoll. A crucial provision of the MOU is that resettlement will occur only if no person returning to Rongelap and substituting on a native-foods-only diet will receive a calculated annual whole-body radiation dose equivalent of more than 100 mrem above background. The MOU also presents an action level of 17 pCi/g for the concentration of transuranic contamination, i.e., plutonium and americium, in soils below which mitigation will be considered unnecessary

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

    International Nuclear Information System (INIS)

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

    2013-01-01

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

  3. 24 CFR 115.206 - Performance assessments; Performance standards.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 1 2010-04-01 2010-04-01 false Performance assessments; Performance standards. 115.206 Section 115.206 Housing and Urban Development Regulations Relating to Housing... AGENCIES Certification of Substantially Equivalent Agencies § 115.206 Performance assessments; Performance...

  4. Bone age assessment practices in infants and older children among Society for Pediatric Radiology members

    International Nuclear Information System (INIS)

    Breen, Micheal A.; Tsai, Andy; Stamm, Aymeric; Kleinman, Paul K.

    2016-01-01

    Numerous bone age estimation techniques exist, but little is known about what methods radiologists use in clinical practice. To determine which methods pediatric radiologists use to assess bone age in children, and their confidence in these methods. Society for Pediatric Radiology (SPR) members were invited to complete an online survey regarding bone age assessment. Respondents were asked to identify the methods used and their confidence with their technique for the following groups: Infants (<1 year old), 1- to 3-year-olds and 3- to 18-year-olds. Of the 937 SPR members invited, 441 responded (47%). For infants, 70% of respondents use the hand/wrist method of Greulich and Pyle, 27% use a hemiskeleton method (e.g., Sontag or Elgenmark), and 14.4% use the knee method of Pyle and Hoerr. Of these respondents, 34% were not confident with their technique. For 1- to 3-year-olds, 86% used Greulich and Pyle, and 19% used a hemiskeleton method; 21% were not confident with their technique in this age group. For 3- to 18-year-olds, 97% used Greulich and Pyle, and only 6% of respondents were not confident with their technique in this category. A logistic regression analysis demonstrated that the chronological age of the patient had the greatest impact on reader confidence, with the odds ratios for confidence being 4 times greater in the 3- to 18-year-olds category compared to the younger groups. For children older than 3 years, the majority of pediatric radiologists are very confident in their use of Greulich and Pyle for bone age assessment. However a variety of methodologies are used when assessing bone age in infants and younger children, and pediatric radiologists are less confident assessing bone age in these children. This survey highlights the need for a consensus protocol on bone age assessment of younger children and infants that provides readers with a higher degree of confidence. (orig.)

  5. Electronic and Social Media-based Radiology Learning Initiative: Development, Implementation, Viewership Trends, and Assessment at 1 Year.

    Science.gov (United States)

    Koontz, Nicholas A; Hill, Danielle V; Dodson, Sean C; Capps, Alisha E; Kamer, Aaron P; Frank, Mark S; Heitkamp, Darel E

    2018-06-01

    We report the development of a new "Case of the Day" (COTD) educational initiative using email, social media (SoMe), and a website to disseminate content, as well as its trends in viewership and assessment of utility for the first year of implementation. Using an image-rich format, a new unknown case was disseminated to radiology trainees and attendings at our institution by email twice per week, including history, salient images, and follow-up questions. Simultaneously, content was externally disseminated on Twitter and a publicly viewable departmental website. On subsequent days, the answer was posted via email, Twitter, and website in the form of a brief YouTube video lecture. Viewership data were collected over the first 12 months (July 1, 2016 to June 30, 2017), and an anonymous survey of participants was performed. Sixty-five COTDs had complete viewership data and were included in our analysis, yielding 4911 "case" email views (mean = 76), 3798 "answer" email views (mean = 58), 68,034 "case" Twitter impressions (mean = 1047), 75,724 "answer" Twitter impressions (mean = 1164), 5465 "case" Twitter engagements (mean = 84), and 5307 "answer" Twitter engagements (mean = 82). COTD YouTube video lectures garnered 3657 views (mean = 61) amounting to 10,358 minutes of total viewing time. Viewers were very satisfied with COTD quality, with 97% (n = 63) reporting the quality as "good" or "excellent." Email and SoMe can serve as effective tools for disseminating radiology educational content. SoMe offers substantial external visibility and branding potential for programs. Copyright © 2018 The Association of University Radiologists. Published by Elsevier Inc. All rights reserved.

  6. Emergency radiology

    International Nuclear Information System (INIS)

    Keats, T.E.

    1986-01-01

    This book is the German, translated version of the original published in 1984 in the U.S.A., entitled 'Emergency Radiology'. The publication for the most part is made up as an atlas of the radiological images presenting the findings required for assessment of the emergency cases and their first treatment. The test parts' function is to explain the images and give the necessary information. The material is arranged in seven sections dealing with the skull, the facial part of the skull, the spine, thorax, abdominal region, the pelvis and the hip, and the limbs. With 690 figs [de

  7. Value-Based Assessment of Radiology Reporting Using Radiologist-Referring Physician Two-Way Feedback System-a Design Thinking-Based Approach.

    Science.gov (United States)

    Shaikh, Faiq; Hendrata, Kenneth; Kolowitz, Brian; Awan, Omer; Shrestha, Rasu; Deible, Christopher

    2017-06-01

    In the era of value-based healthcare, many aspects of medical care are being measured and assessed to improve quality and reduce costs. Radiology adds enormously to health care costs and is under pressure to adopt a more efficient system that incorporates essential metrics to assess its value and impact on outcomes. Most current systems tie radiologists' incentives and evaluations to RVU-based productivity metrics and peer-review-based quality metrics. In a new potential model, a radiologist's performance will have to increasingly depend on a number of parameters that define "value," beginning with peer review metrics that include referrer satisfaction and feedback from radiologists to the referring physician that evaluates the potency and validity of clinical information provided for a given study. These new dimensions of value measurement will directly impact the cascade of further medical management. We share our continued experience with this project that had two components: RESP (Referrer Evaluation System Pilot) and FRACI (Feedback from Radiologist Addressing Confounding Issues), which were introduced to the clinical radiology workflow in order to capture referrer-based and radiologist-based feedback on radiology reporting. We also share our insight into the principles of design thinking as applied in its planning and execution.

  8. Making Performance Assessments a Part of Accountability

    Science.gov (United States)

    Haun, Billy

    2018-01-01

    The purpose of this commentary is to describe recent efforts in Virginia to develop and use performance assessments, including the challenges that emerged during this process and key considerations for states that integrate performance assessment into their systems. Performance assessments can play an important role in preparing students for…

  9. Assessment of Natural Radioactivity and its Radiological Impact in Ortum Region in Kenya

    International Nuclear Information System (INIS)

    Wanjala, F.O.; Otwoma, D.; Kitao, T.F.; Hashim, N.O.

    2015-01-01

    The earth contains natural background radiations originating from terrestrial and cosmic sources. This study aims at assessing the levels of background radiation in air, soil and water and its associated radiological impact and also determines the elemental concentration of the rocks and soils around Ortum hills and quarry. 100 points will be measured for radioactivity in the air and 40 soil and 10 water samples will be collected for laboratory analysis using both grid and purposive sampling methods. Radioactivity in the field will be determined using the hand held Red Eye and Radiagem radiation survey meters. The levels of naturally occurring radionuclide Uranium-238 ( 238 U), Thorium-232 ( 232 Th) and Potassium-40 ( 40 K) in the soil and rocks will be determined using High Pure Germanium (HPGe) detector; the Liquid Scintillation Counter (LSC) will be used for analysis of water samples while the Energy Dispersive X-Ray Fluorescence Spectrometer (EDXRF) will be used to determine the elemental composition in the rocks and soil. The Residual Radioactivity (RESRAD) program will be used to analyze and assess the doses and risks associated with radiation exposure in Ortum region. (author)

  10. Radiological assessment of the inferior alveolar artery course in human corpse mandibles

    Energy Technology Data Exchange (ETDEWEB)

    Bertl, Kristina [Medical University of Vienna, Division of Oral Surgery, Bernhard Gottlieb School of Dentistry, Vienna (Austria); Malmoe University, Department of Periodontology, Faculty of Odontology, Malmoe (Sweden); Hirtler, Lena [Medical University of Vienna, Center for Anatomy and Cell Biology, Department of Systematic Anatomy, Vienna (Austria); Dobsak, Toni [Medical University of Vienna, Division of Oral Surgery, Bernhard Gottlieb School of Dentistry, Vienna (Austria); Medical University of Vienna, Karl Donath Laboratory for Hard Tissue and Biomaterial Research, Division of Oral Surgery, Vienna (Austria); Austrian Cluster for Tissue Regeneration, Vienna (Austria); Heimel, Patrick [Medical University of Vienna, Karl Donath Laboratory for Hard Tissue and Biomaterial Research, Division of Oral Surgery, Vienna (Austria); Austrian Cluster for Tissue Regeneration, Vienna (Austria); Ludwig Boltzmann Institute for Clinical and Experimental Traumatology, Vienna (Austria); Gahleitner, Andre [Medical University of Vienna, Division of Oral Surgery, Bernhard Gottlieb School of Dentistry, Vienna (Austria); Medical University of Vienna, Department of Diagnostic Radiology, Division of Osteoradiology, General Hospital, Vienna (Austria); Ulm, Christian [Medical University of Vienna, Division of Oral Surgery, Bernhard Gottlieb School of Dentistry, Vienna (Austria); Plenk, Hanns [Medical University of Vienna, Bone and Biomaterials Research, Institute for Histology and Embryology, Vienna (Austria)

    2015-04-01

    CT assessment of the entire course of the inferior alveolar artery (IAA) within the mandibular canal. After contrast medium injection (180 or 400 mg/ml iodine concentration) into the external carotid arteries of 15 fresh human cadaver heads, the main IAA's position in the canal (cranial, buccal, lingual or caudal) was assessed in dental CT images of partially edentulous mandibles. The course of the main IAA could be followed at both iodine concentrations. The higher concentration gave the expected better contrast, without creating artefacts, and improved visibility of smaller arteries, such as anastomotic sections, dental branches and the incisive branch. The main IAA changed its position in the canal more often than so far known (mean 4.3 times, SD 1.24, range 2-7), but with a similar bilateral course. A cranial position was most often detected (42 %), followed by lingual (36 %), caudal (16 %) and buccal (6 %). With this non-invasive radiologic method, the entire course of the main IAA in the mandibular canal could be followed simultaneously with other bone structures on both sides of human cadaver mandibles. This methodology allows one to amend existing anatomical and histological data, which are important for surgical interventions near the mandibular canal. (orig.)

  11. Compared assessment of chemical risk and radiological risk for the environment

    International Nuclear Information System (INIS)

    Beaugelin-Seiller, K.; Garnier-Laplace, J.

    2007-01-01

    The environmental protection is today a global issue that concerns all the human activities. The challenge is to be able to prove their compatibility with the protection of the natural environment, but also if required to manage adequately a potential or established risk, generally in the context of ever strict regulations. Regarding the chemical aspects, known methods are available for the assessment of the associated risk for the environment. From the radiological point of view, the necessity to have such tools recently became more apparent, in order to justify for the public and with a full transparency the release of radioactive substances into the environment, to meet the requirements of the new regulations in terms of environmental protection and finally to harmonize the approaches between human and environmental radioprotection as well as between chemical and radioactive pollutants, simultaneously present for example in routine releases from nuclear power plants. At this end of harmonization, the assessment methodologies of the environmental risk linked to radionuclides or chemical substances are exposed from the theory to their comparative application, a new approach under development from which the first results are summarised. (authors)

  12. Radiological assessment of the inferior alveolar artery course in human corpse mandibles

    International Nuclear Information System (INIS)

    Bertl, Kristina; Hirtler, Lena; Dobsak, Toni; Heimel, Patrick; Gahleitner, Andre; Ulm, Christian; Plenk, Hanns

    2015-01-01

    CT assessment of the entire course of the inferior alveolar artery (IAA) within the mandibular canal. After contrast medium injection (180 or 400 mg/ml iodine concentration) into the external carotid arteries of 15 fresh human cadaver heads, the main IAA's position in the canal (cranial, buccal, lingual or caudal) was assessed in dental CT images of partially edentulous mandibles. The course of the main IAA could be followed at both iodine concentrations. The higher concentration gave the expected better contrast, without creating artefacts, and improved visibility of smaller arteries, such as anastomotic sections, dental branches and the incisive branch. The main IAA changed its position in the canal more often than so far known (mean 4.3 times, SD 1.24, range 2-7), but with a similar bilateral course. A cranial position was most often detected (42 %), followed by lingual (36 %), caudal (16 %) and buccal (6 %). With this non-invasive radiologic method, the entire course of the main IAA in the mandibular canal could be followed simultaneously with other bone structures on both sides of human cadaver mandibles. This methodology allows one to amend existing anatomical and histological data, which are important for surgical interventions near the mandibular canal. (orig.)

  13. Experienced in Conducting Radiological Impact Assessment (RIA) in Oil and Gas Industry

    International Nuclear Information System (INIS)

    Khairuddin Mohamad Kontol; Ismail Sulaiman; Azmi Hassan; Faizal Azrin Abdul Razalim

    2011-01-01

    Oil and gas industry is a major contributor to the nation economy. Oil sludge and scales produced during production contain enhanced naturally occurring radioactive material (NORM).All the oil sludge and scales are temporarily stored at the crude oil terminal premise. Sludge and scales are under the jurisdiction of Department of Environment (DOE) and Atomic Energy Licensing Board (AELB).AELB has issued a guideline regarding the disposal of sludge and scales as in (LEM/TEK/30, 1996). In this guideline, Radiological Impact Assessment (RIA) should be carried out on all proposed disposals and demonstrate that no member of public will be exposed to more than 1 mSv/y. Malaysian Nuclear Agency (Nuclear Malaysia) has the expertise and capability to conduct the RIA. Nuclear Malaysia has been conducting RIA for local and international oil and gas companies operated in Malaysia. Recently, AELB has issued code of practice on radiation protection for oil and gas industry (LEM/TEK/58, 2009). In this code of practice, RIA shall be conducted to assess the dose received by a critical group of public as a result of the disposal of oil sludge and scale higher than 3 Bq/g Total Activity Concentration (TAC). For exemption by AELB, the RIA calculated dose shall not exceed 0.3 mSv/y. (author)

  14. Post-closure performance assessment treatment of the biosphere

    Energy Technology Data Exchange (ETDEWEB)

    Broderick, M A [UK Nirex Ltd., Harwell, Oxfordshire (United Kingdom); Egan, M J [AEA Technology, Risley, Cheshire (United Kingdom); Thorne, M C [Electrowatt, Horsham, Sussex (United Kingdom); Williams, J A [AEA Technology, Risley, Cheshire (United Kingdom)

    1996-07-01

    The Nirex strategy for radioactive waste disposal is based on a system of engineered and natural barriers, providing long-term isolation of the waste from those parts of the environment that are in contact with or readily available for use by humans (i.e. the biosphere). Even so, there remains the possibility that, on a timescale of thousands to tens of thousands of years, small quantities of poorly-sorbed, long-lived radionuclides may be released from the engineered disposal system, ultimately to emerge into the biosphere. Biosphere models are used in post-closure performance assessments to quantify the competing effects of dilution and accumulation processes on radionuclide concentrations in the accessible environment. Understanding biosphere processes and their time dependence is necessary not only to determine the radiological impact of possible future releases, but also to characterise the dynamics of transport in groundwater and the location, duration and extent of any such releases. Nirex is developing a new biosphere model for use in post-closure radiological assessments for the proposed Sellafield repository. A compartment modelling approach has been adopted, as in studies performed previously, but the system will be dynamic, allowing changes with time in both the properties of compartments and the transfers between compartments. The transport model considers both mass transport within the biosphere and the migration of radionuclides, thereby ensuring that a self-consistent description of the biosphere, in a spatially-extensive domain is maintained. The above approach is designed to link the assessment models used by the Nirex assessment team more closely into the Nirex biosphere research programme than has hitherto been possible with time-invariant assessment models. (author)

  15. Post-closure performance assessment treatment of the biosphere

    International Nuclear Information System (INIS)

    Broderick, M.A.; Egan, M.J.; Thorne, M.C.; Williams, J.A.

    1996-01-01

    The Nirex strategy for radioactive waste disposal is based on a system of engineered and natural barriers, providing long-term isolation of the waste from those parts of the environment that are in contact with or readily available for use by humans (i.e. the biosphere). Even so, there remains the possibility that, on a timescale of thousands to tens of thousands of years, small quantities of poorly-sorbed, long-lived radionuclides may be released from the engineered disposal system, ultimately to emerge into the biosphere. Biosphere models are used in post-closure performance assessments to quantify the competing effects of dilution and accumulation processes on radionuclide concentrations in the accessible environment. Understanding biosphere processes and their time dependence is necessary not only to determine the radiological impact of possible future releases, but also to characterise the dynamics of transport in groundwater and the location, duration and extent of any such releases. Nirex is developing a new biosphere model for use in post-closure radiological assessments for the proposed Sellafield repository. A compartment modelling approach has been adopted, as in studies performed previously, but the system will be dynamic, allowing changes with time in both the properties of compartments and the transfers between compartments. The transport model considers both mass transport within the biosphere and the migration of radionuclides, thereby ensuring that a self-consistent description of the biosphere, in a spatially-extensive domain is maintained. The above approach is designed to link the assessment models used by the Nirex assessment team more closely into the Nirex biosphere research programme than has hitherto been possible with time-invariant assessment models. (author)

  16. Technology assessment HTR. Part 6. The radiological risks associated with the thorium-fuelled High Temperature Reactor. A comparative risk evaluation

    International Nuclear Information System (INIS)

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

    1996-06-01

    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 fuel led LWR cycle was used. The structure of the report is as follows. In Chapter 2 the general methodology for assessing the radiological risks associated with nuclear installations is described. An overview is given of the measures commonly used to quantify these risks. In Chapter 3 an overview is given of the different stages of the reference uranium fuel led LWR cycle and the thorium fuel led HTGR cycle. In Chapter 4 a stage-by-stage analysis is given of the radiological risks associated with the two fuel cycles. Finally, in Chapter 5 an evaluation is made of the radiological risks associated with the LWR and HTGR cycles and with thorium and uranium fuels. In Appendix A the production and releases of 14 C for LWR and HTGR fuel cycle facilities is considered in detail. 11 figs., 10 tabs., 10 refs

  17. Adaptation of the dynamic model for radiological assessment of nuclear accident in rural area under conditions of tropical climate

    International Nuclear Information System (INIS)

    Vinhas, Denise Martins

    2004-01-01

    Following an accidental release of radionuclides to the atmosphere that leads to the contamination of large areas, a detailed and fast methodology to assess the prognosis of public exposure is needed, in order to estimate radiological consequences and propose and optimize decisions related to the protection of the public. The model ECOSYS has been chosen to integrate the SIEM, the Integrated Emergency System developed by IRD/CNEN, to assess the doses at the short, medium and long term to the public after an accidental contamination of rural areas. The objective of this work is to perform the adaptation of the model ECOSYS to be used in Brazil to assess public exposure and support decision processes regarding the implementation of protective measures but also to guide the need for studies and research aiming to improve the adequacy of estimates to the actual Brazilian situation. The area select for reference to this work consists on the 50 km radius area surrounding the Brazilian nuclear power plants, located at Angra dos Reis County, in the state of Rio de Janeiro. The methodology included the definition of criteria to select agricultural cultures and animals to be simulated, taking into account both the availability of the production at the selected area and the relevance of the food to the population regional diet. Radionuclides included in this study were 137 Cs, 90 Sr and 131 I. A large survey has been performed to gather data related to both agricultural practices and behavior of radionuclides in the selected agricultural-systems. The results of simulation indicated the relevance of the knowledge of local aspects on the estimated doses. Important factors included the kind of products produced, seasonality, agricultural practices, animals feed practices, kind of soil, and ingestion habits of the population. (author)

  18. Assessing the Gap in Female Authorship in Radiology: Trends Over the Past Two Decades.

    Science.gov (United States)

    Liang, Teresa; Zhang, Cathy; Khara, Rohan M; Harris, Alison C

    2015-07-01

    The aim of this study was to retrospectively identify trends in the representation of female authorship in prominent general radiology journals over the past 2 decades. A comprehensive search was conducted for all articles published in 1993, 2003, and 2013 in Radiology, the American Journal of Roentgenology (AJR), European Radiology, and Investigative Radiology. The genders of the first and last authors were collected. Chi-square tests were used for statistical analysis, and P values authorship, 24.7% of first authors, and 15.2% of senior authors. The average overall female first and senior authorship grew from 19.7% to 32.1% and from 13.6% to 19.1%, respectively from 1993 to 2013. Female first authorship grew over the past 2 decades in the journals reviewed, with significant growth in AJR and Radiology (P authorship in the individual journals grew from 16.4%-29.1% in 1993, to 29.1%-34.8% in 2013. Female senior authorship also demonstrated growth in the past 2 decades, growing from 4.3%-17.5% in 1993 to 15.5%-23.2% in 2013. There was significant growth in senior female authorship in Radiology (from 12.1% to 19.2%, P = .004) and European Radiology (from 4.3% to 15.5%, P = .0433). Female senior authorship remained significantly lower than first authorship over the past 2 decades (P = .002, P authorship in radiology literature is proportional to their growth in the specialty, they continue to remain a minority, especially in senior authorship, and demonstrate similar participation to other medical specialties. Copyright © 2015 American College of Radiology. Published by Elsevier Inc. All rights reserved.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-09-01

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

  20. 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)

  1. Radiological Assessment for the Removal of Legacy BPA Power Lines that Cross the Hanford Site

    International Nuclear Information System (INIS)

    Millsap, William J.; Brush, Daniel J.

    2013-01-01

    This paper discusses some radiological field monitoring and assessment methods used to assess the components of an old electrical power transmission line that ran across the Hanford Site between the production reactors area (100 Area) and the chemical processing area (200 Area). This task was complicated by the presence of radon daughters -- both beta and alpha emitters -- residing on the surfaces, particularly on the surfaces of weathered metals and metals that had been electrically-charged. In many cases, these activities were high compared to the DOE Surface Contamination Guidelines, which were used as guides for the assessment. These methods included the use of the Toulmin model of argument, represented using Toulmin diagrams, to represent the combined force of several strands of evidences, rather than a single measurement of activity, to demonstrate beyond a reasonable doubt that no or very little Hanford activity was present and mixed with the natural activity. A number of forms of evidence were used: the overall chance of Hanford contamination; measurements of removable activity, beta and alpha; 1-minute scaler counts of total surface activity, beta and alpha, using 'background makers'; the beta activity to alpha activity ratios; measured contamination on nearby components; NaI gamma spectral measurements to compare uncontaminated and potentially-contaminated spectra, as well as measurements for the sentinel radionuclides, Am- 241 and Cs-137 on conducting wire; comparative statistical analyses; and in-situ measurements of alpha spectra on conducting wire showing that the alpha activity was natural Po-210, as well as to compare uncontaminated and potentially-contaminated spectra

  2. Radiological Assessment for the Removal of Legacy BPA Power Lines that Cross the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Millsap, William J.; Brush, Daniel J.

    2013-11-13

    This paper discusses some radiological field monitoring and assessment methods used to assess the components of an old electrical power transmission line that ran across the Hanford Site between the production reactors area (100 Area) and the chemical processing area (200 Area). This task was complicated by the presence of radon daughters -- both beta and alpha emitters -- residing on the surfaces, particularly on the surfaces of weathered metals and metals that had been electrically-charged. In many cases, these activities were high compared to the DOE Surface Contamination Guidelines, which were used as guides for the assessment. These methods included the use of the Toulmin model of argument, represented using Toulmin diagrams, to represent the combined force of several strands of evidences, rather than a single measurement of activity, to demonstrate beyond a reasonable doubt that no or very little Hanford activity was present and mixed with the natural activity. A number of forms of evidence were used: the overall chance of Hanford contamination; measurements of removable activity, beta and alpha; 1-minute scaler counts of total surface activity, beta and alpha, using "background makers"; the beta activity to alpha activity ratios; measured contamination on nearby components; NaI gamma spectral measurements to compare uncontaminated and potentially-contaminated spectra, as well as measurements for the sentinel radionuclides, Am- 241 and Cs-137 on conducting wire; comparative statistical analyses; and in-situ measurements of alpha spectra on conducting wire showing that the alpha activity was natural Po-210, as well as to compare uncontaminated and potentially-contaminated spectra.

  3. Performance study of the primary standard ionization chamber for deployment of the diagnostic radiology qualities

    International Nuclear Information System (INIS)

    Cardoso, Ricardo de Souza; Bossio, Francisco; Quaresma, Daniel da Silva; Peixoto, Jose Guilherme Pereira

    2013-01-01

    Activities radiotherapy, diagnostic radiology and radiation protection, require knowledge of physical and dosimetric parameters, to be applied safely. Aiming to meet demand in Brazil, the National Laboratory of Metrology of Ionising Radiation - LNMRI - is deploying the primary standard for the calibration of secondary standard chambers, used in quality control in hospitals, clinics and industries. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-06-01

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

  5. Quantification of radionuclide transfer in terrestrial and freshwater environments for radiological assessments

    International Nuclear Information System (INIS)

    2009-05-01

    For more than thirty years, the IAEA has published a set of documents aimed at the limitation of the radiation exposure of the population from various nuclear activities. In particular, in 1994 the IAEA published Technical Reports Series No. 364, Handbook of Parameter Values for the Prediction of Radionuclide Transfer in Temperate Environments. Over the years, it has proved to be a valuable reference for radioecologists, modellers and authorities in Member States, and has been quoted in numerous impact assessments. Technical Reports Series No. 364 was based on a review of available data up to the end of 1992. However, a number of high quality critical reviews have been produced in recent years for some of the transfer parameter values which merit consideration. Thus, it was assumed that there is sufficient new information available to warrant reconsideration of a significant proportion of the values given in Technical Reports Series No. 364 and to initiate an updating of Technical Reports Series No. 364 in the framework of the IAEA EMRAS (Environmental Modelling for RAdiation Safety) project. It is expected that the revision of Technical Reports Series No. 364 will initiate further updating of related IAEA publications, and international and national radiological models. The present IAEA-TECDOC is intended to be a support to the update of Technical Reports Series No. 364, overcoming the limitations of the former, and comprises both revised transfer parameter values, as well as missing data, key transfer processes, concepts and models that were found to be important for radiation safety

  6. ARANO - a computer program for the assessment of radiological consequences of atmospheric radioactive releases

    International Nuclear Information System (INIS)

    Savolainen, I.; Vuori, S.

    1980-09-01

    A short description of the calculation possibilities, methods and of the structure of the computer code system ARANO is given, in addition to the input quide. The code can be employed in the calculation of environmental radiological consequences caused by radioactive materials released to atmosphere. Results can be individual doses for different organs at given distances from the release point, collective doses, numbers of persons exceeding given dose limits, numbers of casualties, areas polluted by deposited activity and losses of investments or production due to radioactive contamination. Both a case with a single release and atmospheric dispersion situation and a group of radioactive release and dispersions with discrete probability distributions can be considered. If the radioactive releases or the dispersion conditions are described by probability distributions, the program assesses the magnitudes of the specified effects in all combinations of the release and dispersion situations and then calculates the expectation values and the cumulative probability distributions of the effects. The vertical mixing in the atmosphere is described with a Ksub(Z)-model. In the lateral direction the plume is assumed to be Gaussian, and the release duration can be taken into account in the σsub(y)-values. External gamma dose from the release plume is calculated on the basis of a data file which has been created by 3-dimensional integration. Dose due to inhalation and due to gamma radiation from the contaminated ground are calculated by using appropriate dose conversion factors, which are collected into two mutually alternative block data subprograms. (author)

  7. 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)

  8. Correlations of radiological assessment of skeletal maturity and orthopaedic injuries in the standardbred

    International Nuclear Information System (INIS)

    Pasolini, M.P.; Meomartino, L.; Fatone, G.; Brunetti, A.; Laratta, I.

    2003-01-01

    The aim of this study was to define a correlation between the incidence of orthopaedic injuries and the skeletal maturity, radiologically assessed, in a group of 23 standardbred horses. Starting at 18 months of age, radiograms of calcaneus and distal radial physis were taken at two months intervals, until X-ray evidence of closure. All the physis were blindly graded as: C: open physis; B-: initial evidence of central closure; B: partially closed physis; B+: full closure of the central portion of the physis; A: closed physis. Based on this classification, the horses were grouped as I (immature subject - C, B- and B), or M (mature subject - B+ and A). Orthopaedic injuries were classified as major lesion, if causing prolonged or definitive interruption of training, or minor, if causing brief or no interruption of training. Estimation of injury incidence in the different groups was calculated using the chi-square test (significance level P0.01). The average ages of physis closure (mean +- SD) were 24.1 +- 2.6 months (range 19-28), for the calcaneal physis, and 28.2 +- 2 months (range 26-33), for the distal radial physis, without significant differences between colts and fillies. In our study, according to a previous report, no correlation between X-ray skeletal maturity and incidence of orthopaedic injuries was demonstrated [it

  9. 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)

  10. Radiological assessment for the dumping of radioactive wastes in the oceans

    International Nuclear Information System (INIS)

    Templeton, W.L.

    1993-06-01

    Over the last three decades or so, a number of international meetings have been convened to treat the specific problem of radioactive waste disposal into the oceans. The first of these meetings was held in 1958 at the United Nations Conference on the Law of the Sea. Immediately following, the International Atomic Energy Agency (IAEA), in the Brynielsson Report, recommended measures for ensuring that disposal of radioactive waste into the sea would not result in unacceptable hazards to man (IAEA 1961). Since that time, major changes have occurred in the philosophy and recommendations of the International Commission on Radiological Protection that are crucial to the assessments of impacts arising from this practice. Knowledge of oceanographic processes has improved markedly, providing better understanding of the physical transport process and of the pathways by which radionuclides are transported from marine dumping and disposal sites back to man. Finally, radioecology has developed to the stage where predictions of radionuclide cycling pathways and rates are possible. The IAEA report of 1961 was revised in 1983 (IAEA 1983). The IAEA has published many documents (Safety Series and Technical Documents) covering relevant areas such as oceanographic models, bioaccumulation factors, sediment distribution coefficients, and effects of ionizing radiation on organisms

  11. Contractor Performance Assessment Reporting System

    Data.gov (United States)

    US Agency for International Development — CPARS is a web-based system used to input data on contractor performance. Reports from the system are used as an aid in awarding contracts to contractors that...

  12. Patient Evaluation and Preparation in Vascular and Interventional Radiology: What Every Interventional Radiologist Should Know (Part 1: Patient Assessment and Laboratory Tests)

    Energy Technology Data Exchange (ETDEWEB)

    Taslakian, Bedros, E-mail: btaslakian@gmail.com [NYU Langone Medical Center, Department of Radiology (United States); Sebaaly, Mikhael Georges, E-mail: ms246@aub.edu.lb; Al-Kutoubi, Aghiad, E-mail: mk00@aub.edu.lb [American University of Beirut Medical Center, Department of Diagnostic Radiology (Lebanon)

    2016-03-15