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Sample records for radiological assessment applied

  1. Methodology for environmental radiological assessment applied to the decommissioning of the Italian Nuclear Power Plants

    International Nuclear Information System (INIS)

    Petraglia, A.; Sabbarese, C.; Terrasi, F.; D'Onofrio, A.; Visciano, L.; Alfieri, S.; Esposito, A.M.; Migliore, G.; Mancini, F.; Napier, B.

    2006-01-01

    The present study is the second part of a program of characterization of the sites surrounding the Italian Nuclear Power Plants (NPPs) which are currently involved in decommissioning activities. In the first phase of the project an analysis of the Garigliano NPP was carried out and the reference groups of the population were established on the basis of a socio-economical survey of the site. A field campaign was carried out aiming to assess the 'zero level' due to the natural and past anthropogenic radioactivity [1, 2]. In the second part the study was extended to the other three Italian NPPs, namely Latina, Trino and Caorso. The radiological doses due to the planned and accidental releases during the decommissioning phases were calculated on the basis of environmental parameters related to the area of interest. These parameters include climatological, hydrological, geo morphological data. The implementation of transport and diffusion specific models of radionuclides in the environment was another step for the dose calculation using specific evaluation software. The current software (V.A.D.O.S.C.A.) specially built and used in the past for Italian NPPs has been replaced by the framework F.R.A.M.E.S.-GenII 2.0 which is a calculation code updated in the transport model and in the reference laws, and running under new computer operating systems. This code has been used to design the possible scenarios for each site by using conceptual calculation models which contain local input data and adequate dispersion models. The input data consist of (a) way and amount of radionuclide release in planned and accidental cases, (b) reference groups of population and their food habits, (c) climatic data of the area understudy. The dispersion models are implemented by considering releases in water (canal, river, sea) and in atmosphere. In order to allow a simplified, efficient and friendly utilisation of the Frames-GenII code, it has been enriched with a routine, D.S.A.-Reader, which

  2. 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

  3. 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...

  4. Making the link between radiological assessment, nuclear safety assessment and environmental impact assessment, as applied to unloading of the Lepse spent fuel storage vessel

    International Nuclear Information System (INIS)

    Smith, Graham M.; Sneve, Malgorzata K.; Markarov, Valentine G.

    2000-01-01

    Planning and optimisation of radioactive waste management operations is a complicated task involving scientific, technical and social issues. There are many factors which have to be balanced, involving trade-offs such as those between safety now and long term safety; between protection of human health and protection of the environment as a whole; between protection of workers and protection of the public; and between mitigation of risks of major accidents and mitigation of routine low-level but certain to occur risks. Managing the spent fuel currently stored on the Lepse vessel in Murmansk offers as big a challenge as any other in this context. The Russian Federation state regulatory process imposes strict requirements on operators to demonstrate adequate safety, environmental and human health protection. Practically, however, there is little experience in Russia or elsewhere on how to combine all the issues referred to above within an overall assessment that leads to informed decision making. The paper will describe the components of assessment work being considered within the context of the regulatory planning of Lepse unloading operations. The scope will focus on radiation protection issues but also include non-radioactive pollution risks and other safety issues have to be taken into account if a truly optimal allocation and application of resources is to be made. Consideration will be given to radiation worker dose and other health risk assessments for routine operations, safety assessments of special operations such as spent fuel handling; and the radiological and other environmental and human health impacts of planned releases of effluents to the biosphere. The need to identify and collate particular relevant information will discussed and the links between the different components of the overall assessment will be identified with a view to improving the overall effectiveness of the assessment process. The problem of combining all the information coherently

  5. 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

  6. 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

  7. 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

  8. 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)

  9. Applying industrial engineering practices to radiology.

    Science.gov (United States)

    Rosen, Len

    2004-01-01

    Seven hospitals in Oregon and Washington have successfully adopted the Toyota Production System (TPS). Developed by Taiichi Ohno, TPS focuses on finding efficiencies and cost savings in manufacturing processes. A similar effort has occurred in Canada, where Toronto's Hospital for Sick Children has developed a database for its diagnostic imaging department built on the principles of TPS applied to patient encounters. Developed over the last 5 years, the database currently manages all interventional patient procedures for quality assurance, inventory, equipment, and labor. By applying industrial engineering methodology to manufacturing processes, it is possible to manage these constraints, eliminate the obstacles to achieving streamlined processes, and keep the cost of delivering products and services under control. Industrial engineering methodology has encouraged all stakeholders in manufacturing plants to become participants in dealing with constraints. It has empowered those on the shop floor as well as management to become partners in the change process. Using a manufacturing process model to organize patient procedures enables imaging department and imaging centers to generate reports that can help them understand utilization of labor, materials, equipment, and rooms. Administrators can determine the cost of individual procedures as well as the total and average cost of specific procedure types. When Toronto's Hospital for Sick Children first implemented industrial engineering methodology to medical imaging interventional radiology patient encounters, it focused on materials management. Early in the process, the return on investment became apparent as the department improved its management of more than 500,000 dollars of inventory. The calculated accumulated savings over 4 years for 10,000 interventional procedures alone amounted to more than 140,000 dollars. The medical imaging department in this hospital is only now beginning to apply what it has learned to

  10. 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.

  11. 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

  12. 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

  13. 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

  14. Dosimetry applied to radiology and radiotherapy

    International Nuclear Information System (INIS)

    Yoshimura, Elisabeth Mateus

    2010-01-01

    Full text. The uses of ionizing radiation in medicine are increasing worldwide, and the population doses increase as well. The actual radiation protection philosophy is based on the balance of risks and benefits related to the practices, and patient dosimetry has an important role in the implementation of this point of view. In radiology the goal is to obtain an image with diagnostic quality with the minimum patient dose. In modern Radiotherapy the cure indexes are higher, giving rise to longer survival times to the patients. Dosimetry in radiotherapy helps the treatment planning systems to get a better protection to critical organs, with higher doses to the tumor, with a guarantee of better life quality to the patient. We will talk about the new trends in dosimetry of medical procedures, including experimental techniques and calculation tools developed to increase reliability and precision of dose determination. In radiology the main concerns of dosimetry are: the transition from film- radiography to digital image, the pediatric patient doses, and the choice of dosimetric quantities to quantify fluoroscopy and tomography patient doses. As far as Radiotherapy is concerned, there is a search for good experimental techniques to quantify doses to tissues adjacent to the target volumes in patients treated with new radiotherapy techniques, as IMRT and heavy particle therapy. (author)

  15. 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

  16. 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

  17. Applying 'Evidence-Based Medicine' Theory to Interventional Radiology.Part 2: A Spreadsheet for Swift Assessment of Procedural Benefit and Harm

    International Nuclear Information System (INIS)

    MacEneaney, Peter M.; Malone, Dermot E.

    2000-01-01

    AIM: To design a spreadsheet program to analyse interventional radiology (IR) data rapidly produced in local research or reported in the literature using 'evidence-based medicine' (EBM) parameters of treatment benefit and harm. MATERIALS AND METHODS: Microsoft Excel TM was used. The spreadsheet consists of three worksheets. The first shows the 'Levels of Evidence and Grades of Recommendations' that can be assigned to therapeutic studies as defined by the Oxford Centre for EBM. The second and third worksheets facilitate the EBM assessment of therapeutic benefit and harm. Validity criteria are described. These include the assessment of the adequacy of sample size in the detection of possible procedural complications. A contingency (2 x 2) table for raw data on comparative outcomes in treated patients and controls has been incorporated. Formulae for EBM calculations are related to these numerators and denominators in the spreadsheet. The parameters calculated are benefit -- relative risk reduction, absolute risk reduction, number needed to treat (NNT). Harm -- relative risk, relative odds, number needed to harm (NNH). Ninety-five per cent confidence intervals are calculated for all these indices. The results change automatically when the data in the therapeutic outcome cells are changed. A final section allows the user to correct the NNT or NNH in their application to individual patients. RESULTS: This spreadsheet can be used on desktop and palmtop computers. The MS Excel TM version can be downloaded via the Internet from the URL ftp://radiography.com/pub/TxHarm00.xls. CONCLUSION: A spreadsheet is useful for the rapid analysis of the clinical benefit and harm from IR procedures. MacEneaney, P.M. and Malone, D.E

  18. The 7 basic tools of quality applied to radiological safety

    International Nuclear Information System (INIS)

    Gonzalez F, J.A.

    1991-01-01

    This work seeks to establish a series of correspondences among the search of the quality and the optimization of the doses received by the occupationally exposed personnel. There are treated about the seven basic statistic tools of the quality: the Pareto technique, Cause effect diagrams, Stratification, Verification sheet, Histograms, Dispersion diagrams and Graphics and control frames applied to the Radiological Safety

  19. 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

  20. Digital processing methodology applied to exploring of radiological images

    International Nuclear Information System (INIS)

    Oliveira, Cristiane de Queiroz

    2004-01-01

    In this work, digital image processing is applied as a automatic computational method, aimed for exploring of radiological images. It was developed an automatic routine, from the segmentation and post-processing techniques to the radiology images acquired from an arrangement, consisting of a X-ray tube, target and filter of molybdenum, of 0.4 mm and 0.03 mm, respectively, and CCD detector. The efficiency of the methodology developed is showed in this work, through a case study, where internal injuries in mangoes are automatically detected and monitored. This methodology is a possible tool to be introduced in the post-harvest process in packing houses. A dichotomic test was applied to evaluate a efficiency of the method. The results show a success of 87.7% to correct diagnosis and 12.3% to failures to correct diagnosis with a sensibility of 93% and specificity of 80%. (author)

  1. 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

  2. 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)

  3. 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

  4. 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

  5. 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...

  6. 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

  7. 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)

  8. THE IMPORTANCE OF APPLIED TO BIO-SECURITY PROFESSIONAL RADIOLOGY

    Directory of Open Access Journals (Sweden)

    Mauro Trevisan

    2013-09-01

    Full Text Available This study highlights the importance of biosecurity in the work of technicians and technologists in Radiology. As a means of motivation research, it was observed that despite the investment of the hospitals and clinics for the improvement of radiological techniques, little has been done to prevent the spread of diseases among the professionals in radiology. To do so, held the same direction by quantitatively and qualitatively, using the analytical method and a questionnaire as the technique of analysis, with the sample of 29 professionals located in public hospitals, the School LS and in private practice. The results demonstrated that there is knowledge of biosafety among radiology professionals, but there is no understanding of the relevance of the subject by some a good portion of them.

  9. Understanding and Applying the Concept of Value Creation in Radiology.

    Science.gov (United States)

    Larson, David B; Durand, Daniel J; Siegal, Daniel S

    2017-04-01

    The concept of value in radiology has been strongly advocated in recent years as a means of advancing patient care and decreasing waste. This article explores the concept of value creation in radiology and offers a framework for how radiology practices can create value according to the needs of their referring clinicians. Value only exists in the eyes of a customer. We propose that the primary purpose of diagnostic radiology is to answer clinical questions using medical imaging to help guide management of patient care. Because they are the direct recipient of this service, we propose that referring clinicians are the direct customers of a radiology practice and patients are indirect customers. Radiology practices create value as they understand and fulfill their referring clinicians' needs. To narrow those needs to actionable categories, we propose a framework consisting of four major dimensions: (1) how quickly the clinical question needs to be answered, (2) the degree of specialization required to answer the question, (3) how often the referring clinician uses imaging, and (4) the breadth of imaging that the referring clinician uses. We further identify three major settings in which referring clinicians utilize radiological services: (1) emergent or urgent care, (2) primary care, and (3) specialty care. Practices best meet these needs as they engage with their referring clinicians, create a shared vision, work together as a cohesive team, structure the organization to meet referring clinicians' needs, build the tools, and continually improve in ways that help referring clinicians care for patients. Copyright © 2016 American College of Radiology. Published by Elsevier Inc. All rights reserved.

  10. 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

  11. Decision theory applied to image quality control in radiology.

    Science.gov (United States)

    Lessa, Patrícia S; Caous, Cristofer A; Arantes, Paula R; Amaro, Edson; de Souza, Fernando M Campello

    2008-11-13

    The present work aims at the application of the decision theory to radiological image quality control (QC) in diagnostic routine. The main problem addressed in the framework of decision theory is to accept or reject a film lot of a radiology service. The probability of each decision of a determined set of variables was obtained from the selected films. Based on a radiology service routine a decision probability function was determined for each considered group of combination characteristics. These characteristics were related to the film quality control. These parameters were also framed in a set of 8 possibilities, resulting in 256 possible decision rules. In order to determine a general utility application function to access the decision risk, we have used a simple unique parameter called r. The payoffs chosen were: diagnostic's result (correct/incorrect), cost (high/low), and patient satisfaction (yes/no) resulting in eight possible combinations. Depending on the value of r, more or less risk will occur related to the decision-making. The utility function was evaluated in order to determine the probability of a decision. The decision was made with patients or administrators' opinions from a radiology service center. The model is a formal quantitative approach to make a decision related to the medical imaging quality, providing an instrument to discriminate what is really necessary to accept or reject a film or a film lot. The method presented herein can help to access the risk level of an incorrect radiological diagnosis decision.

  12. 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

  13. 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

  14. 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)

  15. 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

  16. 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)

  17. 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.

  18. 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 ...

  19. 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

  20. 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

  1. 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)

  2. Cooperative learning as applied to resident instruction in radiology reporting.

    Science.gov (United States)

    Mueller, Donald; Georges, Alexandra; Vaslow, Dale

    2007-12-01

    The study is designed to evaluate the effectiveness of an active form of resident instruction, cooperative learning, and the residents' response to that form of instruction. The residents dictated three sets of reports both before and after instruction in radiology reporting using the cooperative learning method. The reports were evaluated for word count, Flesch-Kincaid grade level, advancement on clinical spectrum, clarity, and comparison to prior reports. The reports were evaluated for changes in performance characteristics between the pre- and postinstruction dictations. The residents' response to this form of instruction was evaluated by means of a questionnaire. The instruction was effective in changing the resident dictations. The results became shorter (Pcooperative learning activities. The least positive responses related to the amount of time devoted to the project. Sixty-three percent of respondents stated that the time devoted to the project was appropriate. Cooperative learning can be an effective tool in the setting of the radiology residency. Instructional time requirements must be strongly considered in designing a cooperative learning program.

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

    International Nuclear Information System (INIS)

    Thome, D.J.

    1995-01-01

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

  4. Federal Radiological Monitoring and Assessment Center Phased Response Operations

    International Nuclear Information System (INIS)

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

    1999-01-01

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

  5. 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.

  6. 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.

  7. 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

  8. 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

  9. 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

  10. 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

  11. 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)

  12. Uncertainty quantification applied to the radiological characterization of radioactive waste.

    Science.gov (United States)

    Zaffora, B; Magistris, M; Saporta, G; Chevalier, J-P

    2017-09-01

    This paper describes the process adopted at the European Organization for Nuclear Research (CERN) to quantify uncertainties affecting the characterization of very-low-level radioactive waste. Radioactive waste is a by-product of the operation of high-energy particle accelerators. Radioactive waste must be characterized to ensure its safe disposal in final repositories. Characterizing radioactive waste means establishing the list of radionuclides together with their activities. The estimated activity levels are compared to the limits given by the national authority of the waste disposal. The quantification of the uncertainty affecting the concentration of the radionuclides is therefore essential to estimate the acceptability of the waste in the final repository but also to control the sorting, volume reduction and packaging phases of the characterization process. The characterization method consists of estimating the activity of produced radionuclides either by experimental methods or statistical approaches. The uncertainties are estimated using classical statistical methods and uncertainty propagation. A mixed multivariate random vector is built to generate random input parameters for the activity calculations. The random vector is a robust tool to account for the unknown radiological history of legacy waste. This analytical technique is also particularly useful to generate random chemical compositions of materials when the trace element concentrations are not available or cannot be measured. The methodology was validated using a waste population of legacy copper activated at CERN. The methodology introduced here represents a first approach for the uncertainty quantification (UQ) of the characterization process of waste produced at particle accelerators. Copyright © 2017 Elsevier Ltd. All rights reserved.

  13. Anti-scatter grids, applied in diagnostic radiology

    International Nuclear Information System (INIS)

    Porubszky, T.

    2012-01-01

    During imaging in diagnostic radiology, X-ray beam is scattered on all media between X-ray source and X-ray image receptor. The most important one from these is the patient itself. Scattered radiation, reaching X-ray image receptor - which may be even 5-6 times more intensive than X-ray pattern, in case of pelvis of a corpulent patient - reduces image contrast, impairs detail visibility and, moreover - in case of examinations during which staff stays in the controlled area, it causes radiation exposure of the staff. For diminishing scattered radiation, in principle, there are two possibilities. One of them is the so-called air gap, i.e. increasing the distance between the patient and the X-ray image receptor; however, because of the geometric magnification it is not always applicable or appropriate. The other way is application of anti-scatter grids directly in front of the X-ray image receptor. Interest of the patient is firstly the image, appropriate for diagnosis, and only after it the possible lowest radiation exposure. In most cases radiation exposure is optimized if image quality impairing effect of scattered radiation is decreased, although entrance skin dose and so radiation exposure of the patient may increase then by a factor of 2 to 5. Examinations of babies and small children as well as extremities, however, are exceptions: in these cases antiscatter grids are to be removed from the beam as amount of scattered radiation is very small, therefore optimizing radiation exposure in these cases reached by examination without grid. The presentation deals with the most important characteristics of anti-scatter grids as new edition of their international standard will be published next year. (author)

  14. 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

  15. 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.)

  16. 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)

  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. 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

  19. 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.

  20. Optimized delivery radiological reports: applying Six Sigma methodology to a radiology department.

    Science.gov (United States)

    Cavagna, Enrico; Berletti, Riccardo; Schiavon, Francesco; Scarsi, Barbara; Barbato, Giuseppe

    2003-03-01

    To optimise the process of reporting and delivering radiological examinations with a view to achieving 100% service delivery within 72 hours to outpatients and 36 hours to inpatients. To this end, we used the Six Sigma method which adopts a systematic approach and rigorous statistical analysis to analyse and improve processes, by reducing variability and minimising errors. More specifically, our study focused on the process of radiological report creation, from the end of the examination to the time when the report is made available to the patient, to examine the bottlenecks and identify the measures to be taken to improve the process. Six Sigma uses a five-step problem-solving process called DMAIC, an acronym for Define, Measure, Analyze, Improve and Control. The first step is to define the problem and the elements crucial to quality, in terms of Total Quality Control. Next, the situation is analysed to identify the root causes of the problem and determine which of these is most influential. The situation is then improved by implementing change. Finally, to make sure that the change is long-lasting, measures are taken to sustain the improvements and obtain long-term control. In our case we analysed all of the phases the report passes through before reaching the user, and studied the impact of voice-recognition reporting on the speed of the report creation process. Analysis of the information collected showed that the tools available for report creation (dictaphone, voice-recognition system) and the transport of films and reports were the two critical elements on which to focus our efforts. Of all the phases making up the process, reporting (from end of examination to end of reporting) and distribution (from the report available to administrative staff to report available to the patient) account for 90% of process variability (73% and 17%, respectively). We further found that the reports dictated into a voice-recognition reporting system are delivered in 45 hours

  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. Statistical sampling applied to the radiological characterization of historical waste

    Directory of Open Access Journals (Sweden)

    Zaffora Biagio

    2016-01-01

    Full Text Available The evaluation of the activity of radionuclides in radioactive waste is required for its disposal in final repositories. Easy-to-measure nuclides, like γ-emitters and high-energy X-rays, can be measured via non-destructive nuclear techniques from outside a waste package. Some radionuclides are difficult-to-measure (DTM from outside a package because they are α- or β-emitters. The present article discusses the application of linear regression, scaling factors (SF and the so-called “mean activity method” to estimate the activity of DTM nuclides on metallic waste produced at the European Organization for Nuclear Research (CERN. Various statistical sampling techniques including simple random sampling, systematic sampling, stratified and authoritative sampling are described and applied to 2 waste populations of activated copper cables. The bootstrap is introduced as a tool to estimate average activities and standard errors in waste characterization. The analysis of the DTM Ni-63 is used as an example. Experimental and theoretical values of SFs are calculated and compared. Guidelines for sampling historical waste using probabilistic and non-probabilistic sampling are finally given.

  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. 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

  9. 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

  10. 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)

  11. 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)

  12. 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.

  13. 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)

  14. 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

  15. Radiology education. The evaluation and assessment of clinical competence

    International Nuclear Information System (INIS)

    Hibbert, Kathryn M.; Van Deven, Teresa; Chhem, Rethy K.; Nagasaki Univ.; Wang, Shih-chang; Royal Australian and New Zealand College of Radiologists, Sydney

    2012-01-01

    Third volume of a trilogy devoted to radiology education and improvement of medical imaging students' learning, teaching, and scholarship. Reviews the philosophies, theories, and principles that underpin assessment and evaluation in radiology education. Includes a series of rich case studies. Written by an international group of experienced educators and medical professionals. This book reviews the philosophies, theories, and principles that underpin assessment and evaluation in radiology education, highlighting emerging practices and work done in the field. The sometimes conflicting assessment and evaluation needs of accreditation bodies, academic programs, trainees, and patients are carefully considered. The final section of the book examines assessment and evaluation in practice, through the development of rich case studies reflecting the implementation of a variety of approaches. This is the third book in a trilogy devoted to the scholarship of radiology education and is the culmination of an important initiative to improve medical imaging students' learning, teaching, and scholarship by bringing together experienced educators and medical professionals. The previous two books focused on the culture and the learning organizations in which our future radiologists are educated and on the application of educational principles in the education of radiologists. Here, the trilogy comes full circle: attending to the assessment and evaluation of the education of its members has much to offer back to the learning of the organization.

  16. Radiological/toxicological sabotage assessments at the Savannah River Site

    International Nuclear Information System (INIS)

    Johnson, H.D.; Pascal, M.D.; Richardson, D.L.

    1995-01-01

    This paper describes the methods being employed by Westinghouse Savannah River Company (WSRC) to perform graded assessments of radiological and toxicological sabotage vulnerability at Savannah River Site (SRS) facilities. These assessments are conducted to ensure that effective measures are in place to prevent, mitigate, and respond to a potential sabotage event which may cause an airborne release of radiological/toxicological material, causing an adverse effect on the health and safety of employees, the public, and the environment. Department of Energy (DOE) Notice 5630.3A, open-quotes Protection of Departmental Facilities Against Radiological and Toxicological Sabotage,close quotes and the associated April 1993 DOE-Headquarters guidance provide the requirements and outline an eight-step process for hazardous material evaluation. The process requires the integration of information from a variety of disciplines, including safety, safeguards and security, and emergency preparedness. This paper summarizes WSRC's approach towards implementation of the DOE requirements, and explains the inter-relationships between the Radiological and Toxicological Assessments developed using this process, and facility Hazard Assessment Reports (HAs), Safety Analysis Reports (SARs), and Facility Vulnerability Assessments (VAs)

  17. Core ethical values of radiological protection applied to Fukushima case: reflecting common morality and cultural diversities.

    Science.gov (United States)

    Kurihara, Chieko; Cho, Kunwoo; Toohey, Richard E

    2016-12-01

    The International Commission on Radiological Protection (ICRP) has established Task Group 94 (TG94) to develop a publication to clarify the ethical foundations of the radiological protection system it recommends. This TG identified four core ethical values which structure the system: beneficence and non-maleficence, prudence, justice, and dignity. Since the ICRP is an international organization, its recommendations and guidance should be globally applicable and acceptable. Therefore, first this paper presents the basic principles of the ICRP radiological protection system and its core ethical values, along with a reflection on the variation of these values in Western and Eastern cultural traditions. Secondly, this paper reflects upon how these values can be applied in difficult ethical dilemmas as in the case of the emergency and post-accident phases of a nuclear power plant accident, using the Fukushima case to illustrate the challenges at stake. We found that the core ethical values underlying the ICRP system of radiological protection seem to be quite common throughout the world, although there are some variations among various cultural contexts. Especially we found that 'prudence' would call for somewhat different implementation in each cultural context, balancing and integrating sometime conflicting values, but always with objectives to achieve the well-being of people, which is itself the ultimate aim of the radiological protection system.

  18. 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)

  19. 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.

  20. 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)

  1. 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

  2. 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)

  3. 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

  4. 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

  5. Radiological risk assessment for radioactive contamination at landfill site

    International Nuclear Information System (INIS)

    Devgun, J.S.

    1990-01-01

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

  6. 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)

  7. 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

  8. 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)

  9. 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.

  10. 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

  11. 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

  12. 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.

  13. 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)

  14. 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

  15. Radiological interpretation 2020: Toward quantitative image assessment

    International Nuclear Information System (INIS)

    Boone, John M.

    2007-01-01

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

  16. 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

  17. 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

  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. Workplace-based assessment in radiology-where to now?

    Energy Technology Data Exchange (ETDEWEB)

    Augustine, K. [Department of Radiology, Southmead Hospital, North Bristol NHS Trust, Bristol BS10 5NB (United Kingdom); McCoubrie, P., E-mail: paul.mccoubrie@nbt.nhs.u [Department of Radiology, Southmead Hospital, North Bristol NHS Trust, Bristol BS10 5NB (United Kingdom); Wilkinson, J.R. [Department of Cardiology, St Bartholomew' s Hospital, London (United Kingdom); McKnight, L. [Department of Radiology, Morriston Hospital, Swansea (United Kingdom)

    2010-04-15

    Assessment of doctors is in a state of flux. Traditional methods of assessment have been critically examined and found inherently limited. The wholesale shift towards outcome-orientated education in the last 10 years has led to the relatively rapid development of a radically different method of assessment. This method focuses on assessing what doctors do in everyday practice rather than written or practical simulations. Known collectively as 'workplace-based assessment' tools, these have been embraced in North America, whereas they have been more cautiously adopted in the UK. However, many of these assessment tools have not been rigorously studied and, moreover, few have been specifically developed for assessing radiologists. However, they are likely to be incorporated into radiology training in the near future. This paper critically analyses both the underpinning assumptions behind this method and the evidence behind existing tools, and looks at the work that is required to develop, adopt or adapt such tools for use in radiology.

  1. 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

  2. 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)

  3. 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

  4. 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

  5. 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

  6. 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)

  7. 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)

  8. 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)

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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)

  14. Radiological assessment for bauxite mining and alumina refining.

    Science.gov (United States)

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

    2013-01-01

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

  15. 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.

  16. 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)

  17. 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

  18. Validation of radiological efficiency model applied for the crops/soils contaminated by radiocaesium

    International Nuclear Information System (INIS)

    Montero, M.; Vazquez, C.; Moraleda, M.; Claver, F.

    2000-01-01

    The differences shown in the radiological efficiency applying the same agrochemical interventions on a range of contaminated agricultural scenarios by long-live radionuclides have conducted the radioecological studies to quantify the influence of local characteristics on the soil-to-plant transference. In the framework of the Decision Support Systems for post-accidental environmental restoration, a semi-mechanistic approach has been developed to estimate the soil-to-plant transfer factor from the major properties underlying the bioavailability of radiocaesium in soils and the absorption capacity by the crop. The model describes, for each soil texture class, the effects of time and K status on the transference of radiocaesium to plants. The approach lets to estimate the actual and the available minimum transference and to calculate the optimum amendment warranting the maximum radiological efficiency on an specific soil-crop combination. The parameterization and validation of the model from a database providing information about experimental transference studies for a collection of soil-crop combinations are shown. (Author) 4 refs

  19. 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.)

  20. Problems raised by applying the recommendations of the International Commission on Radiological Protection

    International Nuclear Information System (INIS)

    Jammet, H.; Mechali, D.

    1977-01-01

    The International Commission on Radiological Protection regularly issues recommendations on the basic concepts of radiation protection and the general principles governing their application in the field of occupational exposure, medical and other types of population exposure. Among these recommendations some, such as those concerning dose limits applied to individuals of the population, can be directly taken up in national regulations, yet this is not the usual case and the practical application of protection principles will sometimes raise a number of problems difficult to solve. In particular, this is the case with the principle stating that all exposures shall be kept as low as is reasonably achievable, taking into account economic and social factors. This problem is especially important as it governs the determination of authorized limits. Various approaches for solving it are examined. (author)

  1. The applies specific technical requirements to the services of radiological protection according to the 17025

    Energy Technology Data Exchange (ETDEWEB)

    Marrero Garcia, M.; Fernandez Gomez, I. M.; Prendes Alonso, M.; Molina Perez, D.

    2004-07-01

    The employment in the Center of Radiation Protection and Hygiene (CRPH) of Cuba, of the standard 17025 for the administration of the quality of the calibration laboratories and test that offer services of radiological protection requires of a technical complement to really determine the technical competence. In the standard 17025, the specific requirements, are mentioned in the annex B (with informative character), where it points out that: {sup T}he requirements specified in the standard 17025 are established in general terms and, although they can be applied to all the test laboratories and applications, they could be necessary applications{sup .} In the CRPH these applications are translated in indispensable technical requirements to evaluate the performance of the services of radiological protection that offers, specifically those of personal monitoring, the calibration of instruments and the metrology of radionuclides. Although the standard 17025 is quite rigorous in the evaluation of technical requirements, to have specific materials not serves alone of tool to the laboratories, but also for the body of accreditation . In the CRPH the permanent employment of this tool has not constituted a practice, but had been good before our clients certain nonconformities to evaluate the performance of the laboratory and to achieve the recovery of the trust in its results. With this work we seek to expose some of these experiences. The experiences of the application of some of the technical requirements, in our case, they have been applied to the service of personal monitoring that offers the Laboratory of Personal Dosimetry. This laboratory is accredited by the National Accreditation Board of the Republic of Cuba (NABC) and besides fulfilling that settled down in 17025, the Approaches of Accreditation for test laboratories and calibration and it should also implant that settled down as specific technical requirements for the recognition of technical competence. (Author

  2. 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)

  3. 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.

  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. 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

  6. 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.

  7. The Generalised Ecosystem Modelling Approach in Radiological Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Klos, Richard

    2008-03-15

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

  8. 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

  9. 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

  10. 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)

  11. 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)

  12. 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)

  13. 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)

  14. 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

  15. 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

  16. 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)

  17. Assessment of radiological risks at the ATLAS experiment

    International Nuclear Information System (INIS)

    Zajacova, Z.

    2009-07-01

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

  18. 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

  19. 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

  20. 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

  1. 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)

  2. 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)

  3. 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

  4. 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.)

  5. 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.)

  6. 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)

  7. 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)

  8. 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.

  9. 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

  10. 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

  11. 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

  12. 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

  13. Risk assessment of topically applied products

    DEFF Research Database (Denmark)

    Søborg, Tue; Basse, Line Hollesen; Halling-Sørensen, Bent

    2007-01-01

    The human risk of harmful substances in semisolid topical dosage forms applied topically to normal skin and broken skin, respectively, was assessed. Bisphenol A diglycidyl ether (BADGE) and three derivatives of BADGE previously quantified in aqueous cream and the UV filters 3-BC and 4-MBC were used...... as model compounds. Tolerable daily intake (TDI) values have been established for BADGE and derivatives. Endocrine disruption was chosen as endpoint for 3-BC and 4-MBC. Skin permeation of the model compounds was investigated in vitro using pig skin membranes. Tape stripping was applied to simulate broken...... parameters for estimating the risk. The immediate human risk of BADGE and derivatives in topical dosage forms was found to be low. However, local treatment of broken skin may lead to higher exposure of BADGE and derivatives compared to application to normal skin. 3-BC permeated skin at higher flux than 4-MBC...

  14. 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

  15. 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

  16. Lean manufacturing and Toyota Production System terminology applied to the procurement of vascular stents in interventional radiology.

    Science.gov (United States)

    de Bucourt, Maximilian; Busse, Reinhard; Güttler, Felix; Wintzer, Christian; Collettini, Federico; Kloeters, Christian; Hamm, Bernd; Teichgräber, Ulf K

    2011-08-01

    OBJECTIVES: To apply the economic terminology of lean manufacturing and the Toyota Production System to the procurement of vascular stents in interventional radiology. METHODS: The economic- and process-driven terminology of lean manufacturing and the Toyota Production System is first presented, including information and product flow as well as value stream mapping (VSM), and then applied to an interdisciplinary setting of physicians, nurses and technicians from different medical departments to identify wastes in the process of endovascular stent procurement in interventional radiology. RESULTS: Using the so-called seven wastes approach of the Toyota Production System (waste of overproducing, waiting, transport, processing, inventory, motion and waste of defects and spoilage) as well as further waste characteristics (gross waste, process and method waste, and micro waste), wastes in the process of endovascular stent procurement in interventional radiology were identified and eliminated to create an overall smoother process from the procurement as well as from the medical perspective. CONCLUSION: Economic terminology of lean manufacturing and the Toyota Production System, especially VSM, can be used to visualise and better understand processes in the procurement of vascular stents in interventional radiology from an economic point of view.

  17. 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

  18. 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.

  19. 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

  20. 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

  1. 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.

  2. Applying Systems Engineering Reduces Radiology Transport Cycle Times in the Emergency Department

    Science.gov (United States)

    White, Benjamin A.; Yun, Brian J.; Lev, Michael H.; Raja, Ali S.

    2017-01-01

    Introduction Emergency department (ED) crowding is widespread, and can result in care delays, medical errors, increased costs, and decreased patient satisfaction. Simultaneously, while capacity constraints on EDs are worsening, contributing factors such as patient volume and inpatient bed capacity are often outside the influence of ED administrators. Therefore, systems engineering approaches that improve throughput and reduce waste may hold the most readily available gains. Decreasing radiology turnaround times improves ED patient throughput and decreases patient waiting time. We sought to investigate the impact of systems engineering science targeting ED radiology transport delays and determine the most effective techniques. Methods This prospective, before-and-after analysis of radiology process flow improvements in an academic hospital ED was exempt from institutional review board review as a quality improvement initiative. We hypothesized that reorganization of radiology transport would improve radiology cycle time and reduce waste. The intervention included systems engineering science-based reorganization of ED radiology transport processes, largely using Lean methodologies, and adding no resources. The primary outcome was average transport time between study order and complete time. All patients presenting between 8/2013–3/2016 and requiring plain film imaging were included. We analyzed electronic medical record data using Microsoft Excel and SAS version 9.4, and we used a two-sample t-test to compare data from the pre- and post-intervention periods. Results Following the intervention, average transport time decreased significantly and sustainably. Average radiology transport time was 28.7 ± 4.2 minutes during the three months pre-intervention. It was reduced by 15% in the first three months (4.4 minutes [95% confidence interval [CI] 1.5–7.3]; to 24.3 ± 3.3 min, P=0.021), 19% in the following six months (5.4 minutes, 95% CI [2.7–8.2]; to 23.3 ± 3

  3. 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)

  4. 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

  5. Digital processing methodology applied to exploring of radiological images; Metodologia de processamento digital aplicada a exploracao de imagens radiologicas

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Cristiane de Queiroz

    2004-07-01

    In this work, digital image processing is applied as a automatic computational method, aimed for exploring of radiological images. It was developed an automatic routine, from the segmentation and post-processing techniques to the radiology images acquired from an arrangement, consisting of a X-ray tube, target and filter of molybdenum, of 0.4 mm and 0.03 mm, respectively, and CCD detector. The efficiency of the methodology developed is showed in this work, through a case study, where internal injuries in mangoes are automatically detected and monitored. This methodology is a possible tool to be introduced in the post-harvest process in packing houses. A dichotomic test was applied to evaluate a efficiency of the method. The results show a success of 87.7% to correct diagnosis and 12.3% to failures to correct diagnosis with a sensibility of 93% and specificity of 80%. (author)

  6. Applying radiological emergency planning experience to hazardous materials emergency planning within the nuclear industry

    International Nuclear Information System (INIS)

    Foltman, A.; Newsom, D.; Lerner, K.

    1988-01-01

    The nuclear industry has extensive radiological emergency planning (REP) experience that is directly applicable to hazardous materials emergency planning. Recently, the Feed Materials Production Center near Cincinnati, Ohio, successfully demonstrated such application. The REP experience includes conceptual bases and standards for developing plans that have been tested in hundreds of full-scale exercises. The exercise program itself is also well developed. Systematic consideration of the differences between chemical and radiological hazards shows that relatively minor changes to the REP bases and standards are necessary. Conduct of full-scale, REP-type exercises serves to test the plans, provide training, and engender confidence and credibility

  7. 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)

  8. 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: ...

  9. 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)

  10. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-11-15

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

  12. 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

  13. 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

  14. 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.

  15. MO-DE-201-03: This course presents a review of radiologic anatomy and physiology as it applies to projection radiography, fluoroscopy, CT, MRI, U/S, and nuclear medicine

    International Nuclear Information System (INIS)

    Fahey, F.

    2015-01-01

    Fundamental knowledge of radiologic anatomy and physiology is critical for medical physicists. Many physicists are exposed to this topic only in graduate school, and knowledge is seldom formally evaluated or assessed after Part I of the ABR exam. Successful interactions with clinicians, including surgeons, radiologists, and oncologists requires that the medical physicist possess this knowledge. This course presents a review of radiologic anatomy and physiology as it applies to projection radiography, fluoroscopy, CT, MRI, U/S, and nuclear medicine. We will review structural anatomy, manipulation of tissue contrast, the marriage between anatomy and physiology, and explore how medical imaging exploits normal and pathological processes in the body to generate contrast. Learning Objectives: Review radiologic anatomy. Examine techniques to manipulate tissue contrast in radiology. Integrate anatomy and physiology in molecular imaging

  16. MO-DE-201-03: This course presents a review of radiologic anatomy and physiology as it applies to projection radiography, fluoroscopy, CT, MRI, U/S, and nuclear medicine

    Energy Technology Data Exchange (ETDEWEB)

    Fahey, F.

    2015-06-15

    Fundamental knowledge of radiologic anatomy and physiology is critical for medical physicists. Many physicists are exposed to this topic only in graduate school, and knowledge is seldom formally evaluated or assessed after Part I of the ABR exam. Successful interactions with clinicians, including surgeons, radiologists, and oncologists requires that the medical physicist possess this knowledge. This course presents a review of radiologic anatomy and physiology as it applies to projection radiography, fluoroscopy, CT, MRI, U/S, and nuclear medicine. We will review structural anatomy, manipulation of tissue contrast, the marriage between anatomy and physiology, and explore how medical imaging exploits normal and pathological processes in the body to generate contrast. Learning Objectives: Review radiologic anatomy. Examine techniques to manipulate tissue contrast in radiology. Integrate anatomy and physiology in molecular imaging.

  17. Radiological risk assessment for the public under the loss of medium and large sources using bayesian methodology

    International Nuclear Information System (INIS)

    Kim, Joo Yeon; Jang, Han Ki; Lee, Jai Ki

    2005-01-01

    Bayesian methodology is appropriated for use in PRA because subjective knowledges as well as objective data are applied to assessment. In this study, radiological risk based on Bayesian methodology is assessed for the loss of source in field radiography. The exposure scenario for the lost source presented in U.S. NRC is reconstructed by considering the domestic situation and Bayes theorem is applied to updating of failure probabilities of safety functions. In case of updating of failure probabilities, it shows that 5% Bayes credible intervals using Jeffreys prior distribution are lower than ones using vague prior distribution. It is noted that Jeffreys prior distribution is appropriated in risk assessment for systems having very low failure probabilities. And, it shows that the mean of the expected annual dose for the public based on Bayesian methodology is higher than the dose based on classical methodology because the means of the updated probabilities are higher than classical probabilities. The database for radiological risk assessment are sparse in domestic. It summarizes that Bayesian methodology can be applied as an useful alternative for risk assessment and the study on risk assessment will be contributed to risk-informed regulation in the field of radiation safety

  18. 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 ...

  19. 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

  20. 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

  1. 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.

  2. 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)

  3. 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)

  4. 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

  5. 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.

  6. 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

  7. 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

  8. 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.

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

    International Nuclear Information System (INIS)

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

    2017-01-01

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

  10. 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

  11. 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

  12. 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.

  13. 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.

  14. 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

  15. 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

  16. 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

  17. 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.

  18. 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

  19. 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

  20. 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

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

    International Nuclear Information System (INIS)

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

  2. 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

  3. 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

  4. 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

  5. Assessment of uniformity and signal-to-noise ratio in radiological image intensifier TV systems

    International Nuclear Information System (INIS)

    Malone, J.F.; O'Connor, M.K.; Maher, K.P.

    1985-01-01

    A method of measuring the uniformity of radiological Image Intensifier-TV systems is described. Large non-uniformities were observed in the systems tested. A method of estimating the Signal-to-Noise Ratio in such systems is also presented and applied to characterise the effectiveness of the noise reduction techniques used in digital fluoroscopy. (author)

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

    International Nuclear Information System (INIS)

    Lee, Gab Bock; Chung, Yang Geun

    2008-01-01

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

  7. 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)

  8. 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.

  9. 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.

  10. 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)

  11. 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)

  12. 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

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

    International Nuclear Information System (INIS)

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

    1993-01-01

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

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

    International Nuclear Information System (INIS)

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

    1993-01-01

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

  15. 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.

  16. 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.

  17. 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.

  18. 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.

  19. Applying soil property information for watershed assessment.

    Science.gov (United States)

    Archer, V.; Mayn, C.; Brown, S. R.

    2017-12-01

    The Forest Service uses a priority watershed scheme to guide where to direct watershed restoration work. Initial assessment was done across the nation following the watershed condition framework process. This assessment method uses soils information for a three step ranking across each 12 code hydrologic unit; however, the soil information used in the assessment may not provide adequate detail to guide work on the ground. Modern remote sensing information and terrain derivatives that model the environmental gradients hold promise of showing the influence of soil forming factors on watershed processes. These small scale data products enable the disaggregation of coarse scale soils mapping to show continuous soil property information across a watershed. When this information is coupled with the geomorphic and geologic information, watershed specialists can more aptly understand the controlling influences of drainage within watersheds and focus on where watershed restoration projects can have the most success. A case study on the application of this work shows where road restoration may be most effective.

  20. 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)

  1. 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

  2. Applying social impact assessment to nursing research.

    Science.gov (United States)

    Bradbury-Jones, Caroline; Taylor, Julie

    2014-08-05

    Many nurses need to construct a research proposal at some stage of their career and there are multiple texts that provide guidance on doing so. However, most texts do not provide explicit guidance on the issue of social impact--the effect of research on the social health and wellbeing of individuals, families and communities and on the improved performance of relevant services. This article proposes that social impact should be considered from the beginning of a research project. It outlines a framework for assessing social impact to help strengthen the quality of research proposals and assist nurses constructing the proposal and also those evaluating it, including academic assessors or funding body reviewers. Nursing research should be useful and should have a positive effect on practice. Focusing on social impact can increase the chances of this desirable outcome.

  3. 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)

  4. 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)

  5. 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.

  6. 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

  7. Regulatory and Radiological Assessment of Co-60 Teletherapy Unit ...

    African Journals Online (AJOL)

    Journal of Applied Science and Technology ... of personnel monitoring, operating and emergency procedures up to waste management provision and the definition of responsibilities of staff and their training ... Personnel Monitoring reports on four (4) staff members were also compared with calculated and measured results.

  8. An aerial radiological survey of the EG ampersand G Mound Applied Technologies and surrounding area, Miamisburg, Ohio

    International Nuclear Information System (INIS)

    1992-11-01

    An aerial radiological survey was conducted over EG ampersand G Mound Applied Technologies, Miamisburg, Ohio, during the period of June 9--24, 1989. The purpose of the 41-square-kilometer (16-square-mile) survey was to document the terrestrial gamma environment of the plant and surrounding area. In addition, ground-based exposure rate measurements and soil samples were obtained to support the aerial data. An exposure rate contour map at 1 meter above ground level was.constructed from the gamma data and overlaid on an aerial photograph and map of the area. Exposure rates measured in the area typically ranged from 9 to 11 microroentgens per hour (μR/h)

  9. 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.

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

    International Nuclear Information System (INIS)

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

    2004-01-01

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

  11. 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

  12. 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

  13. 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

  14. 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)

  15. 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

  16. The ICRP principles applied to radiation protection of the patient in diagnostic radiology

    International Nuclear Information System (INIS)

    Carlsson, S.; Mattsson, S.

    1994-01-01

    The International Commission on Radiation Protection (ICRP) has published new recommendations in Publication 60. These take account of the new biological information and trends in the setting of radiation protection standards since 1977. The main principle for radiation protection of the patient is that the exposure should be justified not only at a broad level but also with respect to the individual patient. Protection arrangements should be optimised using reference dose levels as an upper bound of the optimisation process. The reference levels should be applied with flexibility and based on sound clinical judgement. (authors)

  17. The ICRP principles applied to radiation protection of the patient in diagnostic radiology

    Energy Technology Data Exchange (ETDEWEB)

    Carlsson, S [Department of Medical Physics, s-451 80 Uddevalla (Sweden); Mattsson, S [Department of Radiation Physics, University of Lund, S-214 01 Malmo (Sweden)

    1994-12-31

    The International Commission on Radiation Protection (ICRP) has published new recommendations in Publication 60. These take account of the new biological information and trends in the setting of radiation protection standards since 1977. The main principle for radiation protection of the patient is that the exposure should be justified not only at a broad level but also with respect to the individual patient. Protection arrangements should be optimised using reference dose levels as an upper bound of the optimisation process. The reference levels should be applied with flexibility and based on sound clinical judgement. (authors). 7 refs.

  18. 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.

  19. 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.

  20. 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

  1. 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

  2. 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.

  3. 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.

  4. Radiochromic film for dosimetric measurements in radiation shielding composites synthesized for applied in radiology procedures of high dose

    Energy Technology Data Exchange (ETDEWEB)

    Fontainha, C. C. P. [Universidade Federal de Minas Gerais, Departamento de Engenharia Nuclear, Av. Pte. Antonio Carlos 6627, 31270-901 Belo Horizonte, Minas Gerais (Brazil); Baptista N, A. T.; Faria, L. O., E-mail: crissia@gmail.com [Centro de Desenvolvimento da Tecnologia Nuclear / CNEN, Av. Pte. Antonio Carlos 6627, 31270-901 Belo Horizonte, Minas Gerais (Brazil)

    2015-10-15

    Full text: Medical radiology offers great benefit to patients. However, although specifics procedures of high dose, as fluoroscopy, Interventional Radiology, Computed Tomography (CT) make up a small percent of the imaging procedures, they contribute to significantly increase dose to population. The patients may suffer tissue damage. The probability of deterministic effects incidence depends on the type of procedure performed, exposure time, and the amount of applied dose at the irradiated area. Calibrated radiochromic films can identify size and distribution of the radiated fields and measure intensities of doses. Radiochromic films are sensitive for doses ranging from 0.1 to 20 c Gy and they have the same response for X-rays effective energies ranging from 20 to 100 keV. New radiation attenuators materials have been widely investigated resulting in dose reduction entrance skin dose. In this work, Bi{sub 2}O{sub 3} and ZrO{sub 2}:8 % Y{sub 2}O{sub 3} composites were obtained by mixing them with P(VDF-Tr Fe) copolymers matrix from casting method and then characterized by Ftir. Dosimetric measurements were obtained with Xr-Q A2 Gafchromic radiochromic films. In this setup, one radiochromic film is directly exposed to the X-rays beam and another one measures the attenuated beam were exposed to an absorbed dose of 10 mGy of RQR5 beam quality (70 kV X-ray beam). Under the same conditions, irradiated Xr-Q A2 films were stored and scanned measurement in order to obtain a more reliable result. The attenuation factors, evaluated by Xr-Q A2 radiochromic films, indicate that both composites are good candidates for use as patient radiation shielding in high dose medical procedures. (Author)

  5. 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)

  6. 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)

  7. 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

  8. 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

  9. 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)

  10. 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

  11. 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.

  12. 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.

  13. 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

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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

  20. 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

  1. 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

  2. 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.

  3. 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)

  4. 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)

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

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  6. 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

  7. 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

  8. Virtual anthropology: useful radiological tools for age assessment in clinical forensic medicine and thanatology.

    Science.gov (United States)

    Dedouit, Fabrice; Saint-Martin, Pauline; Mokrane, Fatima-Zohra; Savall, Frédéric; Rousseau, Hervé; Crubézy, Eric; Rougé, Daniel; Telmon, Norbert

    2015-09-01

    Virtual anthropology consists of the introduction of modern slice imaging to biological and forensic anthropology. Thanks to this non-invasive scientific revolution, some classifications and staging systems, first based on dry bone analysis, can be applied to cadavers with no need for specific preparation, as well as to living persons. Estimation of bone and dental age is one of the possibilities offered by radiology. Biological age can be estimated in clinical forensic medicine as well as in living persons. Virtual anthropology may also help the forensic pathologist to estimate a deceased person's age at death, which together with sex, geographical origin and stature, is one of the important features determining a biological profile used in reconstructive identification. For this forensic purpose, the radiological tools used are multislice computed tomography and, more recently, X-ray free imaging techniques such as magnetic resonance imaging and ultrasound investigations. We present and discuss the value of these investigations for age estimation in anthropology.

  9. 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.

  10. 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

  11. 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.

  12. 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

  13. 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.

  14. 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.

  15. 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

  16. Study of the barite mortar composition and its influence on determination of primary transmission curves applied to diagnostic radiology

    Energy Technology Data Exchange (ETDEWEB)

    Firmino, Sandro F.; Souza, Wedla P. de; Hoff, Gabriela, E-mail: sandro.frmino@pucrs.b, E-mail: wedla.souza@acad.pucrs.b, E-mail: ghoff@pucrs.b [Pontificia Universidade Catolica do Rio Grande do Sul (PUC-RS), Porto Alegre, RS (Brazil). Fac. de Fisica. Grupo de Experimentacao e Simulacao Computacional em Fisica Medica (GESiC); Vilhena, Marco T., E-mail: vilhena@pq.cnpq.b [Universidade Federal do Rio Grande do Sul (UFRGS), Porto Alegre, RS (Brazil). Programa de Pos-Graduacao em Engenharia Mecanica

    2009-07-01

    The transmission of photons is an important parameter used to calculate the shielding material thickness. The method of computational simulation purposed, in this work, was applied to generate transmission curves for different energies for monoenergetic beams, on diagnostic radiology energy range, for values between 60 and 150 keV, in steps of 10 keV; and polienergetics spectra for accelerating tube tensions of 140 kVp and 150 kVp. The polienergetic spectra were selected from the Catalogue of Diagnostic X-Ray Spectra and Other Data [1] and changed using deterministic methods to add Aluminum filtration of 3.0 mm. The main objective of this work was to verify the sensitivity of photons spectra to differences observed on barite mortar composition. The computational universe generated simulates photon spectra irradiating directly a shielding wall. The different barite mortar compositions were defined base on a unique sample analysed using the energy dispersion spectroscopy (EDS) measurements in a Philips XL 30 Scanning Electron Microscope (SEM). The compositions were realized on four different areas of one sample: one on opened field of view and the three others uses focused field of view. It was possible verify differences on transmission curves for the different studied energies and different compositions of barite mortar. We suggest future works to study realistic spectra for different barite mortar compositions commercialized in Brazil. (author)

  17. 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)

  18. 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

  19. 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.

  20. 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)

  1. 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)

  2. 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.

  3. 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.

  4. 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

  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. 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)

  8. 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.

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

    International Nuclear Information System (INIS)

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

    1994-01-01

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

  10. 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

  11. Content-based image retrieval applied to bone age assessment

    Science.gov (United States)

    Fischer, Benedikt; Brosig, André; Welter, Petra; Grouls, Christoph; Günther, Rolf W.; Deserno, Thomas M.

    2010-03-01

    Radiological bone age assessment is based on local image regions of interest (ROI), such as the epiphysis or the area of carpal bones. These are compared to a standardized reference and scores determining the skeletal maturity are calculated. For computer-aided diagnosis, automatic ROI extraction and analysis is done so far mainly by heuristic approaches. Due to high variations in the imaged biological material and differences in age, gender and ethnic origin, automatic analysis is difficult and frequently requires manual interactions. On the contrary, epiphyseal regions (eROIs) can be compared to previous cases with known age by content-based image retrieval (CBIR). This requires a sufficient number of cases with reliable positioning of the eROI centers. In this first approach to bone age assessment by CBIR, we conduct leaving-oneout experiments on 1,102 left hand radiographs and 15,428 metacarpal and phalangeal eROIs from the USC hand atlas. The similarity of the eROIs is assessed by cross-correlation of 16x16 scaled eROIs. The effects of the number of eROIs, two age computation methods as well as the number of considered CBIR references are analyzed. The best results yield an error rate of 1.16 years and a standard deviation of 0.85 years. As the appearance of the hand varies naturally by up to two years, these results clearly demonstrate the applicability of the CBIR approach for bone age estimation.

  12. An Assessment of the radiological vulnerability for Spanish soils; Estimacion de indices de vulnerabilidad radiologica para los suelos peninsulares espanoles

    Energy Technology Data Exchange (ETDEWEB)

    Trueba, C.; Millan, R.; Schimid, T.; Lago, C.; Gutierrez, J. [Ciemat. Madrid (Spain)

    2000-07-01

    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)

  13. 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)

  14. 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.

  15. 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

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

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  17. Competency-Based Teaching in Radiology - Implementation and Evaluation of Interactive Workstation-Based Learning to Apply NKLM-Based Content.

    Science.gov (United States)

    Koestner, Wolfgang; Otten, Wiebke; Kaireit, Till; Wacker, Frank K; Dettmer, Sabine

    2017-11-01

    .. · Students report improved understanding of imaging anatomy and radiological findings.. · Interactive case presentation with a DICOM viewer fosters competency-based learning.. Citation Format · Koestner W, Otten W, Kaireit T et al. Competency-Based Teaching in Radiology - Implementation and Evaluation of Interactive Workstation-Based Learning to Apply NKLM-Based Content. Fortschr Röntgenstr 2017; 189: 1076 - 1085. © Georg Thieme Verlag KG Stuttgart · New York.

  18. 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)

  19. 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

  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 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

  2. 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

  3. 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

  4. 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

  5. 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)

  6. 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

  7. 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)

  8. 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

  9. The Swedish radiological environmental protection regulations applied in a review of a license application for a geological repository for spent nuclear fuel.

    Science.gov (United States)

    Andersson, Pål; Stark, Karolina; Xu, Shulan; Nordén, Maria; Dverstorp, Björn

    2017-11-01

    For the first time, a system for specific consideration of radiological environmental protection has been applied in a major license application in Sweden. In 2011 the Swedish Nuclear Fuel & Waste Management Co. (SKB) submitted a license application for construction of a geological repository for spent nuclear fuel at the Forsmark site. The license application is supported by a post-closure safety assessment, which in accordance with regulatory requirements includes an assessment of environmental consequences. SKB's environmental risk assessment uses the freely available ERICA Tool. Environmental media activity concentrations needed as input to the tool are calculated by means of complex biosphere modelling based on site-specific information gathered from site investigations, as well as from supporting modelling studies and projections of future biosphere conditions in response to climate change and land rise due to glacial rebound. SKB's application is currently being reviewed by the Swedish Radiation Safety Authority (SSM). In addition to a traditional document review with an aim to determine whether SKB's models are relevant, correctly implemented and adequately parametrized, SSM has performed independent modelling in order to gain confidence in the robustness of SKB's assessment. Thus, SSM has used alternative stylized reference biosphere models to calculate environmental activity concentrations for use in subsequent exposure calculations. Secondly, an alternative dose model (RESRAD-BIOTA) is used to calculate doses to biota that are compared with SKB's calculations with the ERICA tool. SSM's experience from this review is that existing tools for environmental dose assessment are possible to use in order to show compliance with Swedish legislation. However, care is needed when site representative species are assessed with the aim to contrast them to generic reference organism. The alternative modelling of environmental concentrations resulted in much lower

  10. 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.

  11. 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.)

  12. 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)

  13. 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.

  14. 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.

  15. 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)

  16. 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)

  17. 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)

  18. Quality assurance applied to Radiological Protection Program of CPHR - Centro de Proteccion Y Higiene de las Radiaciones

    International Nuclear Information System (INIS)

    Marrero Garcia, M.; Jova Sed, L.; Domenech Nieves, H.; Hernandez Sainz, A.

    2001-01-01

    The quality assurance in establishment that use ionizing radiation sources, is according to international recommendations of radiation protection programs. This work intends to present the experience of the Centro de Proteccion y Higiene de las Radiaciones (CPHR), in the implementation of requirements of quality in their Radiological Protection Program

  19. 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.)

  20. 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.

  1. 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)

  2. 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

  3. 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

  4. Developments in radiological assessment and biosphere modelling studies to support radioactive waste disposal in Spain

    Energy Technology Data Exchange (ETDEWEB)

    Perez-Sanchez, D. [Centro de Investigaciones Energeticas, Medioambientales y Tecnologicas - CIEMAT (Spain); Thorne, M. [Mike Thorne and Associates Limited (United States)

    2014-07-01

    Long-term safety assessments for the disposal of radioactive waste in Spain involve the demonstration that annual radiation doses to humans due to potential releases of radionuclides from the waste disposal facility into the biosphere will satisfy the regulatory criteria. For several years, CIEMAT has been developing, for ENRESA, a conceptual approach and tool to support modelling of the migration and accumulation of radionuclides within environmental media once those radionuclides have been released to some component of the biosphere (atmosphere, water bodies or soils). The CIEMAT modelling approach calculates the concentrations of radionuclides in different components of the biosphere and then the calculated radionuclide concentrations are used to estimate the radiation doses to humans due to various exposure paths. In this paper, we not only describe the methodology and modelling approach, we also describe recent developments of that approach to better quantify the resultant doses to humans. First, we present recent developments in the mathematical model for the behaviour of {sup 79}Se and {sup 238}U-series radionuclides in soils and their uptake by plants, taking into account seasonal variations in soil hydrology in Spain. Initial studies with the model that are reported here demonstrate that it is a powerful tool for exploring the behaviour of redox-sensitive radionuclides and {sup 238}U decay chain members in soil-plant systems under different hydrological regimes. In particular, it permits studies of the degree to which secular equilibrium assumptions are appropriate when modelling the {sup 238}U decay chain. Further studies are currently being undertaken examining sensitivities of model results to input parameter values and also applying the model to sites contaminated with {sup 238}U-series radionuclides. It is anticipated that results from these studies will also be reported. A particular interest in biosphere safety assessment is how environmental

  5. 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.

  6. 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.

  7. 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)

  8. 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.

  9. 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

  10. 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)

  11. 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

  12. 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.

  13. 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

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

    International Nuclear Information System (INIS)

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

    1991-11-01

    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

  15. 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.

  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. How to Systematically Assess Serious Games Applied to Health Care

    Science.gov (United States)

    Graafland, Maurits; Dankbaar, Mary; Mert, Agali; Lagro, Joep; De Wit-Zuurendonk, Laura; Schuit, Stephanie; Schaafstal, Alma

    2014-01-01

    The usefulness and effectiveness of specific serious games in the medical domain is often unclear. This is caused by a lack of supporting evidence on validity of individual games, as well as a lack of publicly available information. Moreover, insufficient understanding of design principles among the individuals and institutions that develop or apply a medical serious game compromises their use. This article provides the first consensus-based framework for the assessment of specific medical serious games. The framework provides 62 items in 5 main themes, aimed at assessing a serious game’s rationale, functionality, validity, and data safety. This will allow caregivers and educators to make balanced choices when applying a serious game for healthcare purposes. Furthermore, the framework provides game manufacturers with standards for the development of new, valid serious games. PMID:25654163

  18. 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

  19. A REVIEW OF THE FUNDAMENTAL PRINCIPLES OF RADIATION PROTECTION WHEN APPLIED TO THE PATIENT IN DIAGNOSTIC RADIOLOGY.

    Science.gov (United States)

    Moores, B Michael

    2017-06-01

    A review of the role and relevance of the principles of radiation protection of the patient in diagnostic radiology as specified by ICRP has been undertaken when diagnostic risks arising from an examination are taken into account. The increase in population doses arising from diagnostic radiology over the past 20 years has been due to the widespread application of higher dose CT examinations that provide significantly more clinical information. Consequently, diagnostic risks as well as radiation risks need to be considered within the patient radiation protection framework. Justification and optimisation are discussed and the limitations imposed on patient protection by employing only a radiation risk framework is highlighted. The example of radiation protection of the patient in breast screening programmes employing mammography is used to highlight the importance of defined diagnostic outcomes in any effective radiation protection strategy. © The Author 2016. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  20. A review of the fundamental principles of radiation protection when applied to the patient in diagnostic radiology

    International Nuclear Information System (INIS)

    Moores, B. Michael

    2017-01-01

    A review of the role and relevance of the principles of radiation protection of the patient in diagnostic radiology as specified by ICRP has been undertaken when diagnostic risks arising from an examination are taken into account. The increase in population doses arising from diagnostic radiology over the past 20 years has been due to the widespread application of higher dose CT examinations that provide significantly more clinical information. Consequently, diagnostic risks as well as radiation risks need to be considered within the patient radiation protection framework. Justification and optimisation are discussed and the limitations imposed on patient protection by employing only a radiation risk framework is highlighted. The example of radiation protection of the patient in breast screening programmes employing mammography is used to highlight the importance of defined diagnostic outcomes in any effective radiation protection strategy. (author)

  1. Study and radiological impact assessment produced by activities of different non-nuclear industries. Titanium dioxide industries

    International Nuclear Information System (INIS)

    Garcia-Tenorio, R.; Manjon, G.; Abril, J.M.

    2010-01-01

    After a careful study and evaluation of radiological impact, the conclusion is that these industries do not need to be subject to control, and it is not necessary any corrective action to reduce the exposition and/or to apply any radiation protection measures.

  2. 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

  3. 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.

  4. Visual Simultaneous Localization And Mapping (VSLAM) methods applied to indoor 3D topographical and radiological mapping in real-time

    Science.gov (United States)

    Hautot, Felix; Dubart, Philippe; Bacri, Charles-Olivier; Chagneau, Benjamin; Abou-Khalil, Roger

    2017-09-01

    New developments in the field of robotics and computer vision enables to merge sensors to allow fast realtime localization of radiological measurements in the space/volume with near-real time radioactive sources identification and characterization. These capabilities lead nuclear investigations to a more efficient way for operators' dosimetry evaluation, intervention scenarii and risks mitigation and simulations, such as accidents in unknown potentially contaminated areas or during dismantling operations

  5. 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.

  6. 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)

  7. 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)

  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. 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)

  10. 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)

  11. 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)

  12. 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

  13. 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.

  14. 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

  15. 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

  16. 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

  17. Assessment of Radiological and Economic Consequences of a Hypothetical Accident for ETRR-2, Egypt Utilizing COSYMA Code

    International Nuclear Information System (INIS)

    Tawfik, F.S.; Abdel-Aal, M.M.

    2008-01-01

    A comprehensive probabilistic study of an accident consequence assessment (ACA) for loss of coolant accident (LOCA) has accomplished to the second research reactor ETRR-2, located at Inshas Nuclear Research Center, Cairo, Egypt. PC-COSYMA, developed with the support of European Commission, has adopted to assess the radiological and economic consequences of a proposed accident. The consequences of the accident evaluated in case of early and late effects. The effective doses and doses in different organs carried out with and without countermeasures. The force mentioned calculations were required the following studies: the core inventory due to the hypothetical accident, the physical parameters of the source term, the hourly basis meteorological parameters for one complete year, and the population distribution around the plant. The hourly stability conditions and height of atmospheric boundary layers (ABL) of the concerned site were calculated. The results showed that, the nuclides that have short half-lives (few days) give the highest air and ground concentrations after the accident than the others. The area around the reactor requires the early and late countermeasures action after the accident especially in the downwind sectors. Economically, the costs of emergency plan are effectively high in case of applying countermeasures but countermeasures reduce the risk effects

  18. 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)

  19. 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.)

  20. Implications of applying cumulative risk assessment to the workplace.

    Science.gov (United States)

    Fox, Mary A; Spicer, Kristen; Chosewood, L Casey; Susi, Pam; Johns, Douglas O; Dotson, G Scott

    2018-06-01

    Multiple changes are influencing work, workplaces and workers in the US including shifts in the main types of work and the rise of the 'gig' economy. Work and workplace changes have coincided with a decline in unions and associated advocacy for improved safety and health conditions. Risk assessment has been the primary method to inform occupational and environmental health policy and management for many types of hazards. Although often focused on one hazard at a time, risk assessment frameworks and methods have advanced toward cumulative risk assessment recognizing that exposure to a single chemical or non-chemical stressor rarely occurs in isolation. We explore how applying cumulative risk approaches may change the roles of workers and employers as they pursue improved health and safety and elucidate some of the challenges and opportunities that might arise. Application of cumulative risk assessment should result in better understanding of complex exposures and health risks with the potential to inform more effective controls and improved safety and health risk management overall. Roles and responsibilities of both employers and workers are anticipated to change with potential for a greater burden of responsibility on workers to address risk factors both inside and outside the workplace that affect health at work. A range of policies, guidance and training have helped develop cumulative risk assessment for the environmental health field and similar approaches are available to foster the practice in occupational safety and health. Copyright © 2018 Elsevier Ltd. All rights reserved.

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

    International Nuclear Information System (INIS)

    Zajacova, Z.

    2009-01-01

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

  2. 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...

  3. 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

  4. 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)

  5. 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

  6. 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

  7. 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

  8. 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)

  9. An assessment of the radiological impact of coastal erosion of the UK Low-Level Waste Repository - 59137

    International Nuclear Information System (INIS)

    Sumerling, Trevor; Shevelan, John; Cummings, Richard; Fish, Paul; Towler, George; Penfold, James

    2012-01-01

    The UK Low Level Waste Repository Ltd submitted an Environmental Safety Case for the disposal of low-level waste to our regulator, the Environment Agency, on the 1 May 2011. This includes assessments of the long-term radiological safety of past and future disposals. A particular feature of the Low Level Waste Repository (LLWR) is that, because of its proximity to the coast, the site is vulnerable to coastal erosion. Our present understanding is that the site will be eroded on a timescale of a few hundred to a few thousand years, with consequent disruption of the repository, and dispersal of the wastes. We have undertaken a programme of scientific research and monitoring to characterise the evolution and function of the current coastal system that provides a basis for forecasting its future evolution. This has included modelling of contemporary hydrodynamics, geo-morphological mapping, repeat LiDAR and aerial photographic surveys to detect patterns and rates of change, coastal inspections and reconstructions of post-glacial (i.e. last 15, 000 years) sea levels and sediment budgets. Estimates of future sea-level rise have been derived from international sources and consideration given to the impact of such on the local coastline. Two alternative models of coastal recession have then been applied, one empirical and one physical-process based, taking account of the composition of Quaternary-age sediments between the coast and the site and uncertainties in future local sea level change. Comparison of the ranges of calculated times to site contact with sea-level rise indicate that the repository is most likely to be disrupted by undercutting of the engineered vaults and of the trenches. A novel and flexible radiological assessment model has been developed to analyse the impacts of the erosion of the repository and subsequent dispersal of wastes. The model represents the spatial layout of the site and distribution of radionuclides within the repository and is able to take

  10. 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.)

  11. 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

  12. 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)

  13. Evaluation of Current Computer Models Applied in the DOE Complex for SAR Analysis of Radiological Dispersion & Consequences

    Energy Technology Data Exchange (ETDEWEB)

    O' Kula, K. R. [Savannah River Site (SRS), Aiken, SC (United States); East, J. M. [Savannah River Site (SRS), Aiken, SC (United States); Weber, A. H. [Savannah River Site (SRS), Aiken, SC (United States); Savino, A. V. [Savannah River Site (SRS), Aiken, SC (United States); Mazzola, C. A. [Savannah River Site (SRS), Aiken, SC (United States)

    2003-01-01

    The evaluation of atmospheric dispersion/ radiological dose analysis codes included fifteen models identified in authorization basis safety analysis at DOE facilities, or from regulatory and research agencies where past or current work warranted inclusion of a computer model. All computer codes examined were reviewed using general and specific evaluation criteria developed by the Working Group. The criteria were based on DOE Orders and other regulatory standards and guidance for performing bounding and conservative dose calculations. Included were three categories of criteria: (1) Software Quality/User Interface; (2) Technical Model Adequacy; and (3) Application/Source Term Environment. A consensus-based limited quantitative ranking process was used to base an order of model preference as both an overall conclusion, and under specific conditions.

  14. Visual simultaneous localization and mapping (VSLAM) methods applied to indoor 3D topographical and radiological mapping in real-time

    International Nuclear Information System (INIS)

    Hautot, F.; Dubart, P.; Chagneau, B.; Bacri, C.O.; Abou-Khalil, R.

    2017-01-01

    New developments in the field of robotics and computer vision enable to merge sensors to allow fast real-time localization of radiological measurements in the space/volume with near real-time radioactive sources identification and characterization. These capabilities lead nuclear investigations to a more efficient way for operators' dosimetry evaluation, intervention scenarios and risks mitigation and simulations, such as accidents in unknown potentially contaminated areas or during dismantling operations. This paper will present new progresses in merging RGB-D camera based on SLAM (Simultaneous Localization and Mapping) systems and nuclear measurement in motion methods in order to detect, locate, and evaluate the activity of radioactive sources in 3-dimensions

  15. 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

  16. 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)

  17. 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.)

  18. 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)

  19. 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.

  20. 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.)

  1. 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)

  2. 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

  3. 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

  4. Optimal layout of radiological environment monitoring based on TOPSIS method

    International Nuclear Information System (INIS)

    Li Sufen; Zhou Chunlin

    2006-01-01

    TOPSIS is a method for multi-objective-decision-making, which can be applied to comprehensive assessment of environmental quality. This paper adopts it to get the optimal layout of radiological environment monitoring, it is proved that this method is a correct, simple and convenient, practical one, and beneficial to supervision departments to scientifically and reasonably layout Radiological Environment monitoring sites. (authors)

  5. Assessment of 99Tc releases to the atmosphere: a plea for applied research

    International Nuclear Information System (INIS)

    Till, J.E.; Hoffman, F.O.; Dunning, D.E. Jr.

    1978-06-01

    Recent experimental data suggest that the concentration factor for uptake of 99 Tc by vegetation from soils may be two to three orders of magnitude higher than the 0.25 value currently being used in radiological assessments. Following a survey of the literature, a concentration factor of 50 was applied to evaluate the dose from a 1.0 Ci/year release to the atmosphere by a hypothetical uranium enrichment facility. Doses to the GI tract and thyroid of an adult living 1600 m from the facility were 18 millirems and 80 millirems, respectively. These doses are delivered entirely through transport of 99 Tc through food chain pathways. This assessment indicates a potential for 99 Tc exposures to exceed recently proposed standards of the U.S. Environmental Protection Agency in 40 CFR 190. The previously assumed concentration factor of 0.25 would have produced corresponding doses of 0.13 millirem to the GI tract and 0.57 millirem to the thyroid. The results of this analysis demonstrate the need for additional research on the environmental behavior and dosimetry of 99 Tc. In particular, data are needed to elucidate the retention of 99 Tc in soils and the uptake of 99 Tc by edible vegetation in field studies of chronic exposure conditions. Data on the uptake and retention of 99 Tc in humans are also necessary to improve the reliability of dose conversion factors for specific organs and various age groups

  6. User acceptance of a picture archiving and communication system. Applying the unified theory of acceptance and use of technology in a radiological setting.

    Science.gov (United States)

    Duyck, P; Pynoo, B; Devolder, P; Voet, T; Adang, L; Vercruysse, J

    2008-01-01

    The aim of this study is to gain insight into the individual user acceptance of PACS by the radiology department staff of the Ghent University Hospital. Hereto a basic--direct effects only--form of UTAUT was assessed. Ninety-four questionnaires were distributed and 56 usable questionnaires were returned (19 radiologists - 37 technologists). The questionnaire consisted of scales of Venkatesh et al. [13] for performance expectancy (PE), effort expectancy (EE), facilitating conditions (FC), social influence (SI), self-efficacy (SE), attitude (ATT), anxiety (ANX) and behavioral intention (BI), and a scale of Moore et al. [22] to assess the perceived voluntariness of PACS-use. The reliability of all scales, except FC and voluntariness, was acceptable to good. The voluntariness scale was divided into a mandatoriness (MAN) and a voluntariness (VOL) measure. Both radiologists and technologists seem to welcome PACS, with radiologists having higher ratings on PE, EE, ATT, VOL and BI. Only PE and FC were salient for predicting BI, while EE and SI were not salient. Variance explained in behavioral intention to use PACS was 48%. Both radiologists and technologists were positive towards PACS and had strong intentions to use PACS. As other healthcare professionals, they appear to make their technology acceptance decision independent from their superiors, hereby focusing on usefulness rather than on ease of use. It is also important that support is supplied. Basic UTAUT is an adequate model to assess technology acceptance in a radiological setting.

  7. Applying Evolutionary Genetics to Developmental Toxicology and Risk Assessment

    Science.gov (United States)

    Leung, Maxwell C. K.; Procter, Andrew C.; Goldstone, Jared V.; Foox, Jonathan; DeSalle, Robert; Mattingly, Carolyn J.; Siddall, Mark E.; Timme-Laragy, Alicia R.

    2018-01-01

    Evolutionary thinking continues to challenge our views on health and disease. Yet, there is a communication gap between evolutionary biologists and toxicologists in recognizing the connections among developmental pathways, high-throughput screening, and birth defects in humans. To increase our capability in identifying potential developmental toxicants in humans, we propose to apply evolutionary genetics to improve the experimental design and data interpretation with various in vitro and whole-organism models. We review five molecular systems of stress response and update 18 consensual cell-cell signaling pathways that are the hallmark for early development, organogenesis, and differentiation; and revisit the principles of teratology in light of recent advances in high-throughput screening, big data techniques, and systems toxicology. Multiscale systems modeling plays an integral role in the evolutionary approach to cross-species extrapolation. Phylogenetic analysis and comparative bioinformatics are both valuable tools in identifying and validating the molecular initiating events that account for adverse developmental outcomes in humans. The discordance of susceptibility between test species and humans (ontogeny) reflects their differences in evolutionary history (phylogeny). This synthesis not only can lead to novel applications in developmental toxicity and risk assessment, but also can pave the way for applying an evo-devo perspective to the study of developmental origins of health and disease. PMID:28267574

  8. 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.)

  9. 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.)

  10. 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.

  11. 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

  12. 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.

  13. 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.

  14. 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.

  15. 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

  16. 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)

  17. 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)

  18. 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

  19. 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)

  20. 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

  1. 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.

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

    International Nuclear Information System (INIS)

    Robison, W.L.

    1983-04-01

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

  3. A preliminary assessment of the radiological implications of commercial utilization of natural gas from a nuclearly stimulated well

    Energy Technology Data Exchange (ETDEWEB)

    Jacobs, D G; Struxness, E G [Health Physics Division, Oak Ridge National Laboratory, Oak Ridge, TN (United States); Bowman, C R [El Paso Natural Gas Company, El Paso, TX (United States)

    1970-05-01

    Widespread utilization of nuclear explosives, in conjunction with the natural gas industry, can result in radiation exposure of sizable population groups. It is prudent to make realistic assessments of such potential radiation exposures before they occur and, unless the expected exposures are clearly insignificant, to consider these exposures in evaluating the net benefit of this particular use of nuclear energy. All pertinent facts relating to such assessments should be made public and presented in such a way that those who are to assume the risks, if any, can make a reasonable judgment as to whether the risks are acceptable. Radioactivity in natural gas from the Gasbuggy cavity has been analyzed prior to and during flaring operations. None of this gas has entered the collection and distribution system, but a theoretical analysis has been made of the hypothetical impact on members of the public that would have occurred if the gas had been introduced into the commercial stream. Dose equivalents have been estimated for both workers and consumers. In this analysis, Gasbuggy gas has been traced through a real gas-collection system and processing plant, as represented by the present situation existing in the San Juan Production Division, El Paso Natural Gas Company. In addition, a number of considerations are presented which would apply to radiation exposure in metropolitan areas. Results of this analysis for the Gasbuggy well indicate hypothetical dose equivalents to various population groups to be well within the annual dose limits suggested by the International Commission on Radiological Protection. Projection to a steady-state situation involving extensive natural gas production from many producing wells also resulted in hypothetical dose equivalents within the annual dose limits. Simple extrapolation of the results from this analysis to potential exposures resulting from nuclear stimulation of other gas reservoirs cannot be made on a direct basis, but this method

  4. A preliminary assessment of the radiological implications of commercial utilization of natural gas from a nuclearly stimulated well

    International Nuclear Information System (INIS)

    Jacobs, D.G.; Struxness, E.G.; Bowman, C.R.

    1970-01-01

    Widespread utilization of nuclear explosives, in conjunction with the natural gas industry, can result in radiation exposure of sizable population groups. It is prudent to make realistic assessments of such potential radiation exposures before they occur and, unless the expected exposures are clearly insignificant, to consider these exposures in evaluating the net benefit of this particular use of nuclear energy. All pertinent facts relating to such assessments should be made public and presented in such a way that those who are to assume the risks, if any, can make a reasonable judgment as to whether the risks are acceptable. Radioactivity in natural gas from the Gasbuggy cavity has been analyzed prior to and during flaring operations. None of this gas has entered the collection and distribution system, but a theoretical analysis has been made of the hypothetical impact on members of the public that would have occurred if the gas had been introduced into the commercial stream. Dose equivalents have been estimated for both workers and consumers. In this analysis, Gasbuggy gas has been traced through a real gas-collection system and processing plant, as represented by the present situation existing in the San Juan Production Division, El Paso Natural Gas Company. In addition, a number of considerations are presented which would apply to radiation exposure in metropolitan areas. Results of this analysis for the Gasbuggy well indicate hypothetical dose equivalents to various population groups to be well within the annual dose limits suggested by the International Commission on Radiological Protection. Projection to a steady-state situation involving extensive natural gas production from many producing wells also resulted in hypothetical dose equivalents within the annual dose limits. Simple extrapolation of the results from this analysis to potential exposures resulting from nuclear stimulation of other gas reservoirs cannot be made on a direct basis, but this method

  5. Multi-hazard risk assessment applied to hydraulic fracturing operations

    Science.gov (United States)

    Garcia-Aristizabal, Alexander; Gasparini, Paolo; Russo, Raffaella; Capuano, Paolo

    2017-04-01

    Without exception, the exploitation of any energy resource produces impacts and intrinsically bears risks. Therefore, to make sound decisions about future energy resource exploitation, it is important to clearly understand the potential environmental impacts in the full life-cycle of an energy development project, distinguishing between the specific impacts intrinsically related to exploiting a given energy resource and those shared with the exploitation of other energy resources. Technological advances as directional drilling and hydraulic fracturing have led to a rapid expansion of unconventional resources (UR) exploration and exploitation; as a consequence, both public health and environmental concerns have risen. The main objective of a multi-hazard risk assessment applied to the development of UR is to assess the rate (or the likelihood) of occurrence of incidents and the relative potential impacts on surrounding environment, considering different hazards and their interactions. Such analyses have to be performed considering the different stages of development of a project; however, the discussion in this paper is mainly focused on the analysis applied to the hydraulic fracturing stage of a UR development project. The multi-hazard risk assessment applied to the development of UR poses a number of challenges, making of this one a particularly complex problem. First, a number of external hazards might be considered as potential triggering mechanisms. Such hazards can be either of natural origin or anthropogenic events caused by the same industrial activities. Second, failures might propagate through the industrial elements, leading to complex scenarios according to the layout of the industrial site. Third, there is a number of potential risk receptors, ranging from environmental elements (as the air, soil, surface water, or groundwater) to local communities and ecosystems. The multi-hazard risk approach for this problem is set by considering multiple hazards

  6. Radiology today

    International Nuclear Information System (INIS)

    Donner, M.W.; Heuck, F.H.W.

    1981-01-01

    The book encompasses the proceedings of a postgraduate course held in Salzburg in June 1980. 230 radiologists from 17 countries discussed here the important and practical advances of diagnostic radiology, nuclear medicine and ultrasound as they contribute to gastrointestinal, urologic, skeletal, cardiovascular, pediatric, and neuroradiology. The book contains 55 single contributions of different authors to the following main themes: Cardiovascular, Radiology, pulmonary radiology, gastrointestinal radiology, urinary tract radiology, skeletal radiology, mammography, lymphography, ultrasound, ENT radiology, and neuroradiology. (orig./MG)

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

    International Nuclear Information System (INIS)

    Myers, D.K.

    1997-01-01

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

  8. Assessment of management alternatives for LWR wastes. Volume 5. Assessment of the radiological impact to the public resulting from discharges of radioactive effluents

    International Nuclear Information System (INIS)

    Centner, B.

    1993-01-01

    This report deals with the assessment of the radiological impact to the public resulting from discharges of radioactive effluents (liquid and gaseous) in connection with the implementation of the Belgian scenario for the management of PWR waste. Both individual and collective doses have been estimated for a critical group of the population living around the nuclear power plants concerned. This study is part of an overall theoretical exercise aimed at evaluating a selection of management wastes for LWR waste based on economical and radiological criteria

  9. A model for radiological risk assessment from transportation of radioactive material

    International Nuclear Information System (INIS)

    Mancioppi, S.; Piermattei, S.

    1985-01-01

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

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

    CERN Document Server

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

    1983-01-01

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

  11. An assessment of the radiological impact of sea-dumping at the North East Atlantic dump site

    International Nuclear Information System (INIS)

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

    1985-04-01

    This report describes the models and methodology developed for the assessment of the radiological impact of disposal of low and intermediate level waste on the seabed. The development of the waste package model and the combined model of radionuclide dispersion and interactions with sediments in the world's ocean is outlined. This integrated set of models was used for the radiological assessment of sea dumping at the North-East Atlantic site, which formed part of the recent NEA review of the continued suitability of this site. The predicted radiation doses to man are presented, together with the results of the analysis of the sensitivity of the annual individual doses to critical groups to variations in model parameters. (author)

  12. Radiology and fine art.

    Science.gov (United States)

    Marinković, Slobodan; Stošić-Opinćal, Tatjana; Tomić, Oliver

    2012-07-01

    The radiologic aesthetics of some body parts and internal organs have inspired certain artists to create specific works of art. Our aim was to describe the link between radiology and fine art. We explored 13,625 artworks in the literature produced by 2049 artists and found several thousand photographs in an online image search. The examination revealed 271 radiologic artworks (1.99%) created by 59 artists (2.88%) who mainly applied radiography, sonography, CT, and MRI. Some authors produced radiologic artistic photographs, and others used radiologic images to create artful compositions, specific sculptures, or digital works. Many radiologic artworks have symbolic, metaphoric, or conceptual connotations. Radiology is clearly becoming an original and important field of modern art.

  13. Bootstrapping in Applied Linguistics: Assessing Its Potential Using Shared Data

    Science.gov (United States)

    Plonsky, Luke; Egbert, Jesse; Laflair, Geoffrey T.

    2015-01-01

    Parametric analyses such as t tests and ANOVAs are the norm--if not the default--statistical tests found in quantitative applied linguistics research (Gass 2009). Applied statisticians and one applied linguist (Larson-Hall 2010, 2012; Larson-Hall and Herrington 2010), however, have argued that this approach may not be appropriate for small samples…

  14. Radiological assessment of the consequences of the disposal of high-level radioactive waste in subseabed sediments

    International Nuclear Information System (INIS)

    de Marsily, G.; Behrendt, V.; Ensminger, D.A.

    1987-01-01

    The radiological assessment of the seabed option consists in estimating the detriment to man and to the environment that could result from the disposal of high-level waste (HLW) within the seabed sediments in deep oceans. The assessment is made for the high-level waste (vitrified glass) produced by the reprocessing of 10 5 tons of heavy metal from spent fuel, which represents the amount of waste generated by 3333 reactor-yr of 900-MW(electric) reactors, i.e., 3000 GW(electric) x yr. The disposal option considered is to use 14,667 steel penetrators, each of them containing five canisters of HLW glass (0.15 m 3 each). These penetrators would reach a depth of 50 m in the sediments and would be placed at an average distance of 180 m from each other, requiring a disposal area on the order of 22 x 22 km. Two such potential disposal areas in the Atlantic Ocean were studied, Great Meteor East (GME) and South Nares Abyssal Plains (SNAP). A special ship design is proposed to minimize transportation accidents. Approximately 100 shipments would be necessary to dispose of the proposed amount of waste. The results of this radiological assessment seem to show that the disposal of HLW in subseabed sediments is radiologically a very acceptable option

  15. Challenges in radiological impact assessment studies at new sites for nuclear facilities and its safety review and assessment for siting consent

    International Nuclear Information System (INIS)

    Mukherjee Roy, Susmita; Roshan, A.D.; Bishnoi, L.R.

    2018-01-01

    One of the basic requirement of site evaluation for a Nuclear Facility (NF) is radiological impact assessment (RIA). This involves evaluation of transportation of radioactive materials discharged from a nuclear facility under normal operational or accidental conditions, through different compartments of environment viz. air, land and water, and finally assessment of its consequences. Amongst others, site characteristics and the site related parameters play major role in evaluation of impact of postulated releases from NPPs. Doses to public from both external and internal exposures are computed to assess potential consequences of a radiological release and acceptability of the site-plant pair is established based on the outcome of this assessment. A comprehensive study of the site characteristics including meteorology, hydrology, hydro-geology and demography of the region along with details of land and water use, bioaccumulation, transfer to and from the environmental matrices is required for accomplishing satisfactory RIA

  16. Radiological impact assessment for a severe accident scenario for a CANDU 6 type NPP

    International Nuclear Information System (INIS)

    Penescu, Maria; Mehedinteanu, Stefan; Cruceanu, Amalia; Ispas, Georgeta

    2004-01-01

    There are two main categories of consequences of accidental activity releases, which involve radiological considerations. First, there is the health detriment in the exposed population and its descendants; secondly, there is the economic and social impact from the restrictions generated by the control of that population exposure. A variety of health effects may be predicted to occur in an exposed population, depending on the magnitude and distribution of the exposure. Early effects include both death and varying degrees of health impairment, but these are likely to occur only following extremely large activity releases. The major late effects are cancer, both fatal and nonfatal, in the exposed population and heredity effects in their descendants. A variety of radiological endpoints can be calculated to provide a measure of the overall impact. Those, which are considered to be most useful in context of, risk analysis and in the analyses of siting, emergency planning and design criteria can be summarized as: - the incidence of particular health effects in the exposed population and its descendants; - the number of people who may be affected by the application of the countermeasures; - the areas of land beyond particular levels, especially those in which restrictions may be needed with respect of their use or on foodstuffs derived from them; - the economic cost of introducing countermeasures, particularly restrictions on the use of contaminated land and property. A number of countermeasures could be introduced to reduce doses following an accidental release. Such measures are the evacuation and relocation of population and the banning of contaminated food consumption. Sheltering before evacuation is also considered. The criteria for taking the decision to evacuate are based on the total dose and dose for each organ resulted from the exposure to the plume and inhalation, while the criterion for relocation is based simply on the external dose from deposited activity

  17. 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.

  18. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-12-15

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

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

    International Nuclear Information System (INIS)

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

    2003-01-01

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

  1. Assessment of radiological health implicat from ambient environment in the Muar district, Johor, Malaysia

    Science.gov (United States)

    Saleh, Muneer Aziz; Ramli, Ahmad Termizi; Alajerami, Yasser; Mhareb, Mohammad Hasan Abu; Aliyu, Abubakar Sadiq; Gabdo, Hamman Tukur; Garba, Nuraddeen Nasiru

    2014-10-01

    This study aims to obtain baseline data of environmental terrestrial radiation and to assess the corresponding health risk in the ambient environment in Muar District, Johor, Malaysia in view of the possible construction of nuclear power plant (NPP) in the future. The external gamma dose rate (GDR), measured using two portable survey meters, was 151 nGy h-1. The activity concentrations of 232Th, 226Ra, and 40K were determined using hyper pure germanium (HPGe) detector. The activity concentrations were varied from 11±1 to 583±18 Bq kg-1 for 232Th, 6±1 to 244±9 Bq kg-1 for 226Ra, and 13±6 to 830±13 Bq kg-1 for 40K. Various types of water samples were analyzed using a Low Background Alpha Beta Series 5 XLB instrument at Nuclear Malaysia (NM). Gross alpha activity concentrations in tap water varied from 3±1 mBq L-1 to 34±6 mBq L-1 and gross beta activity concentrations varied from 58±5 mBq L-1 to 709±39 mBq L-1 which were lower than the recommended value by Interim National Water Quality Standards for Malaysia (INWQS) and World Health Organization (WHO, 1993). The radiological health which are the annual effective dose equivalent, the collective effective dose, radium equivalent activity and external hazard index 0.220 mSv, 0.526×102 man Sv y-1, 359 Bq kg-1 and 0.969, respectively. The results were comparable to internationally recommended values and discussed accordingly.

  2. Assessment of natural radioactivity and radiological hazards in building materials used in Yan'an, China.

    Science.gov (United States)

    Lu, Xinwei; Li, Nan; Yang, Guang; Zhao, Caifeng

    2013-03-01

    The concentration of natural radionuclides in commonly used building materials collected from Yan'an, China, was determined using gamma ray spectroscopy with a NaI(Tl) detector. The activity concentration of ²²⁶Ra, ²³²Th, and ⁴⁰K in the studied building materials ranges from 9.4-73.1, 11.5-86.9, and 258.9-1,055.1 Bq kg⁻¹, respectively. The concentrations for these natural radionuclides were compared with the reported data of other countries and the world mean values for soil. The radium equivalent activity (Raeq), external hazard index (Hex), internal hazard index (Hin), indoor air absorbed dose rate, and annual effective dose rate due to natural radionuclides in samples were estimated to assess radiological hazards for people living in dwellings made of the studied building materials. The calculated Raeq values of all building materials (75.7-222.1 Bq kg⁻¹) are lower than the limit of 370 Bq kg⁻¹. The values of Hex and Hin are less than unity. The mean values of indoor air absorbed dose rates of all building materials (101.0 ± 14.1-177.0 ± 6.8 nGy h⁻¹) are higher than the world population-weighted average of 84 nGy h⁻¹, while the mean values of annual effective dose range from 0.50 ± 0.07-0.87 ± 0.03 mSv y⁻¹, which are lower than the recommended limit of 1 mSv y⁻¹. It is found that these materials may be used safely as construction materials and do not pose significant radiation hazards to inhabitants.

  3. Assessment of nuclear medicine capabilities in responding to a radiological terrorism event. Technical memorandum

    Energy Technology Data Exchange (ETDEWEB)

    Stodilka, R.Z. [Univ. of Western Ontario, Schulich School of Medicine, London, Ontario (Canada); Wilkinson, D

    2006-09-15

    Substantial effort has been placed into enhancing federal capabilities for responding to a Chemical, Biological, Radiological, or Nuclear (CBRN) terrorist attack. However, little emphasis has been placed on including the local-level medical responders in these efforts. In effecting response to a radiological incident, potentially useful resources to access are health care professionals with training in matters of ionizing radiation, namely: nuclear medicine physicians, radiologists, radiation oncologists, medical physicists, and technologists. In this report, we focus on Nuclear Medicine expertise in Canada, and place this expertise into the context of assisting with a radiological terrorist incident. Nuclear Medicine expertise, along with its supporting infrastructure has already been deployed in proportion to the distribution of the civilian population. Given the expectations that the civilian population places in these health care professionals, their immediate access to specialized equipment, and the delay between a radiological terrorist incident and the arrival of federal expert capabilities, it is likely that these health care professionals will play important roles in emergency response. These roles will likely be: identifying the nature of the incident, triage, decontamination, coordinating with First Responders, and communicating with the media. Acknowledging the potential value of these professionals in responding to a radiological terrorist incident, steps should be taken to enlist their support and integrate them into a coherent national strategy. (author)

  4. Assessment of nuclear medicine capabilities in responding to a radiological terrorism event. Technical memorandum

    International Nuclear Information System (INIS)

    Stodilka, R.Z.; Wilkinson, D.

    2006-09-01

    Substantial effort has been placed into enhancing federal capabilities for responding to a Chemical, Biological, Radiological, or Nuclear (CBRN) terrorist attack. However, little emphasis has been placed on including the local-level medical responders in these efforts. In effecting response to a radiological incident, potentially useful resources to access are health care professionals with training in matters of ionizing radiation, namely: nuclear medicine physicians, radiologists, radiation oncologists, medical physicists, and technologists. In this report, we focus on Nuclear Medicine expertise in Canada, and place this expertise into the context of assisting with a radiological terrorist incident. Nuclear Medicine expertise, along with its supporting infrastructure has already been deployed in proportion to the distribution of the civilian population. Given the expectations that the civilian population places in these health care professionals, their immediate access to specialized equipment, and the delay between a radiological terrorist incident and the arrival of federal expert capabilities, it is likely that these health care professionals will play important roles in emergency response. These roles will likely be: identifying the nature of the incident, triage, decontamination, coordinating with First Responders, and communicating with the media. Acknowledging the potential value of these professionals in responding to a radiological terrorist incident, steps should be taken to enlist their support and integrate them into a coherent national strategy. (author)

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

    International Nuclear Information System (INIS)

    Kim, Ji Young

    2011-02-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ji Young

    2011-02-15

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

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

    International Nuclear Information System (INIS)

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

    1986-06-01

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

  8. Assessment of radiological consequences of routine releases in a site with various nuclear facilities

    International Nuclear Information System (INIS)

    Lucinio, Elena Albeira Guirado

    2003-01-01

    This work evaluates the radiological consequences of a nuclear site with a complex of fuel enrichment, conversion, reconversion facilities and a nuclear reactor. A methodology recommended by the Commission of the European Communities (CEC) is used and implemented in the PC-CREAM computer code. This code is composed of six linked modules, which describe the transfer of radionuclides to the environment, the pathways on which people may be exposed to radiation, and the radiological consequences. Radiation doses to a selected population are evaluated taking into account atmospheric and aquatic releases. (author)

  9. Using SAFRAN Software to Assess Radiological Hazards from Dismantling of Tammuz-2 Reactor Core at Al-tuwaitha Nuclear Site

    Science.gov (United States)

    Abed Gatea, Mezher; Ahmed, Anwar A.; jundee kadhum, Saad; Ali, Hasan Mohammed; Hussein Muheisn, Abbas

    2018-05-01

    The Safety Assessment Framework (SAFRAN) software has implemented here for radiological safety analysis; to verify that the dose acceptance criteria and safety goals are met with a high degree of confidence for dismantling of Tammuz-2 reactor core at Al-tuwaitha nuclear site. The activities characterizing, dismantling and packaging were practiced to manage the generated radioactive waste. Dose to the worker was considered an endpoint-scenario while dose to the public has neglected due to that Tammuz-2 facility is located in a restricted zone and 30m berm surrounded Al-tuwaitha site. Safety assessment for dismantling worker endpoint-scenario based on maximum external dose at component position level in the reactor pool and internal dose via airborne activity while, for characterizing and packaging worker endpoints scenarios have been done via external dose only because no evidence for airborne radioactivity hazards outside the reactor pool. The in-situ measurements approved that reactor core components are radiologically activated by Co-60 radioisotope. SAFRAN results showed that the maximum received dose for workers are (1.85, 0.64 and 1.3mSv/y) for activities dismantling, characterizing and packaging of reactor core components respectively. Hence, the radiological hazards remain below the low level hazard and within the acceptable annual dose for workers in radiation field

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

    International Nuclear Information System (INIS)

    Allott, R.

    2001-01-01

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

  11. Leaching studies of low-level waste as input to radiological assessment at the Drigg disposal site, Cumbria

    International Nuclear Information System (INIS)

    Poulton, J.; Rushbrook, P.E.

    1989-01-01

    Over the period of operation of the low-level waste disposal site at Drigg in Cumbria, several radiological assessments have been carried out. This paper discusses data requirements for such an assessment and in particular describes a project to measure the leaching behaviour of wastes. This project, jointly set up by the staff of BNFL and Environmental Safety Centre at Harwell, began in 1985. The objectives were to determine the processes operating within the waste disposal trenches at Drigg and conditions affecting them. The paper describes the installation and operation of the first of a series of lysimeters designed to simulate conditions in current trenches. (author)

  12. Validation of a physically based catchment model for application in post-closure radiological safety assessments of deep geological repositories for solid radioactive wastes.

    Science.gov (United States)

    Thorne, M C; Degnan, P; Ewen, J; Parkin, G

    2000-12-01

    The physically based river catchment modelling system SHETRAN incorporates components representing water flow, sediment transport and radionuclide transport both in solution and bound to sediments. The system has been applied to simulate hypothetical future catchments in the context of post-closure radiological safety assessments of a potential site for a deep geological disposal facility for intermediate and certain low-level radioactive wastes at Sellafield, west Cumbria. In order to have confidence in the application of SHETRAN for this purpose, various blind validation studies have been undertaken. In earlier studies, the validation was undertaken against uncertainty bounds in model output predictions set by the modelling team on the basis of how well they expected the model to perform. However, validation can also be carried out with bounds set on the basis of how well the model is required to perform in order to constitute a useful assessment tool. Herein, such an assessment-based validation exercise is reported. This exercise related to a field plot experiment conducted at Calder Hollow, west Cumbria, in which the migration of strontium and lanthanum in subsurface Quaternary deposits was studied on a length scale of a few metres. Blind predictions of tracer migration were compared with experimental results using bounds set by a small group of assessment experts independent of the modelling team. Overall, the SHETRAN system performed well, failing only two out of seven of the imposed tests. Furthermore, of the five tests that were not failed, three were positively passed even when a pessimistic view was taken as to how measurement errors should be taken into account. It is concluded that the SHETRAN system, which is still being developed further, is a powerful tool for application in post-closure radiological safety assessments.

  13. An investigation on clinical, radiological and biochemical methods for assessing periodontitis activity

    International Nuclear Information System (INIS)

    Janssen, P.T.M.

    1987-01-01

    In order to recognize in which stage rapidly progressing destruction of periodontal ligament fibers occurs, a number of diagnostic methods are studied in this thesis. It turns out that the actual much utilized clinical methods can not be improved while radiological and biochemical diagnositic methods are much more promising. 106 refs.; 20 figs.; 36 tabs

  14. 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)

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

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  16. Assessment of radiological health implicat from ambient environment in the Muar district, Johor, Malaysia

    International Nuclear Information System (INIS)

    Saleh, Muneer Aziz; Ramli, Ahmad Termizi; Alajerami, Yasser; Mhareb, Mohammad Hasan Abu; Aliyu, Abubakar Sadiq; Gabdo, Hamman Tukur; Garba, Nuraddeen Nasiru

    2014-01-01

    This study aims to obtain baseline data of environmental terrestrial radiation and to assess the corresponding health risk in the ambient environment in Muar District, Johor, Malaysia in view of the possible construction of nuclear power plant (NPP) in the future. The external gamma dose rate (GDR), measured using two portable survey meters, was 151 nGy h −1 . The activity concentrations of 232 Th, 226 Ra, and 40 K were determined using hyper pure germanium (HPGe) detector. The activity concentrations were varied from 11±1 to 583±18 Bq kg −1 for 232 Th, 6±1 to 244±9 Bq kg −1 for 226 Ra, and 13±6 to 830±13 Bq kg −1 for 40 K. Various types of water samples were analyzed using a Low Background Alpha Beta Series 5 XLB instrument at Nuclear Malaysia (NM). Gross alpha activity concentrations in tap water varied from 3±1 mBq L −1 to 34±6 mBq L −1 and gross beta activity concentrations varied from 58±5 mBq L −1 to 709±39 mBq L −1 which were lower than the recommended value by Interim National Water Quality Standards for Malaysia (INWQS) and World Health Organization (WHO, 1993). The radiological health which are the annual effective dose equivalent, the collective effective dose, radium equivalent activity and external hazard index 0.220 mSv, 0.526×10 2 man Sv y −1 , 359 Bq kg −1 and 0.969, respectively. The results were comparable to internationally recommended values and discussed accordingly. - Highlights: • Activity concentration of 232 Th are four times world average. • 232 Th is found to be the main contributor to gamma ray dose in the Muar district. • Gross alpha and beta activity concentrations were lower than the value of WHO. • A digital map plotted for isodose

  17. Assessment of radiological hazards of tin mining and ore processing in Jos, Nigeria

    International Nuclear Information System (INIS)

    Ibeanu, I.

    1999-01-01

    On the Jos Plateau were found uncontrolled tailing heaps generated from Tin Mining Activities. To assess the associated radiological hazards, an abandoned tailing dump ground was investigated with the residents as the critical population. The mean activity concentrations of 4 0K , 226 Ra and 232 Th in the 60 analyzed soil samples were 1251.7±478.4, 3867.5±1282.7 and 8301.9±2862.6 Bqkg -1 , respectively with a mean computed dose rate of 7.2±1.6 μGyh -1 . An annual mean outdoor effective dose of 8.9±0.9mSvy -1 was estimated. Also the activity concentrations of 40 K, 226 Ra and 232 Th in the 60 control soil samples were 447.0±68.0, 37.4±7.4 and 115.4±16.7 Bqkg -1 , respectively with a mean dose rate of 0.11±0.01 μGyh -1 . To account for the internal exposure, vegetables and root crops commonly grown and consumed in the area were assayed. Six varieties of vegetables and five varieties of root crops were analyzed. An internal annual mean effective dose of 148.98±8.14μSvy -1 was estimated. The verification of dose limit compliance for members of the public demands that: External Dose/Dose Limit + Intake (ingested)/ALI (ingestion) + Intake (inhaled)/ALI (inhalation) ≤ 1. Based on obtained data above, there is non-compliance with the dose limit, since the first term of the compliance formula is much greater than unity. There is therefore a need for an intervention to prevent radiation over exposure of the members of the public. The calculated cancer mortality risk for external and internal exposure scenarios for 226 Ra and 232 Th were (1.67±0.33) x 10 -6 (0.00017%) and (3.41±0.14) x 10 -6 (0.00034%), respectively. The 226 Ra radionuclide contributed about 96.09% of the risk in the external scenario with only 3.09% from the 232 Th while in the internal, the 226 Ra contributed only 70.38%. The combined external and internal (ingestion) risk is (5.08±0.36) x 10 -6 /year. (author)

  18. Selecting and applying indicators of ecosystem collapse for risk assessments.

    Science.gov (United States)

    Rowland, Jessica A; Nicholson, Emily; Murray, Nicholas J; Keith, David A; Lester, Rebecca E; Bland, Lucie M

    2018-03-12

    Ongoing ecosystem degradation and transformation are key threats to biodiversity. Measuring ecosystem change towards collapse relies on monitoring indicators that quantify key ecological processes. Yet little guidance is available on selecting and implementing indicators for ecosystem risk assessment. Here, we reviewed indicator use in ecological studies of decline towards collapse in marine pelagic and temperate forest ecosystems. We evaluated the use of indicator selection methods, indicator types (geographic distribution, abiotic, biotic), methods of assessing multiple indicators, and temporal quality of time series. We compared these ecological studies to risk assessments in the International Union for the Conservation of Nature Red List of Ecosystems (RLE), where indicators are used to estimate ecosystem collapse risk. We found that ecological studies and RLE assessments rarely reported how indicators were selected, particularly in terrestrial ecosystems. Few ecological studies and RLE assessments quantified ecosystem change with all three indicator types, and indicators types used varied between marine and terrestrial ecosystem. Several studies used indices or multivariate analyses to assess multiple indicators simultaneously, but RLE assessments did not, as RLE guidelines advise against them. Most studies and RLE assessments used time series spanning at least 30 years, increasing the chance of reliably detecting change. Limited use of indicator selection protocols and infrequent use of all three indicator types may hamper the ability to accurately detect changes. To improve the value of risk assessments for informing policy and management, we recommend using: (i) explicit protocols, including conceptual models, to identify and select indicators; (ii) a range of indicators spanning distributional, abiotic and biotic features; (iii) indices and multivariate analyses with extreme care until guidelines are developed; (iv) time series with sufficient data to

  19. 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

  20. University of Saskatchewan Radiology Courseware (USRC): an assessment of its utility for teaching diagnostic imaging in the medical school curriculum.

    Science.gov (United States)

    Burbridge, Brent; Kalra, Neil; Malin, Greg; Trinder, Krista; Pinelle, David

    2015-01-01

    We have found it very challenging to integrate images from our radiology digital imaging repository into the curriculum of our local medical school. Thus, it has been difficult to convey important knowledge related to viewing and interpreting diagnostic radiology images. We sought to determine if we could create a solution for this problem and evaluate whether students exposed to this solution were able to learn imaging concepts pertinent to medical practice. We developed University of Saskatchewan Radiology Courseware (USRC), a novel interactive web application that enables preclinical medical students to acquire image interpretation skills fundamental to clinical practice. This web application reformats content stored in Medical Imaging Resource Center teaching cases for BlackBoard Learn™, a popular learning management system. We have deployed this solution for 2 successive years in a 1st-year basic sciences medical school course at the College of Medicine, University of Saskatchewan. The "courseware" content covers both normal anatomy and common clinical pathologies in five distinct modules. We created two cohorts of learners consisting of an intervention cohort of students who had used USRC for their 1st academic year, whereas the nonintervention cohort was students who had not been exposed to this learning opportunity. To assess the learning experience of the users we designed an online questionnaire and image review quiz delivered to both of the student groups. Comparisons between the groups revealed statistically significant differences in both confidence with image interpretation and the ability to answer knowledge-based questions. Students were satisfied with the overall usability, functions, and capabilities of USRC. USRC is an innovative technology that provides integration between Medical Imaging Resource Center, a teaching solution used in radiology, and a Learning Management System.

  1. 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)

  2. Regional radiological observations of the environment

    International Nuclear Information System (INIS)

    2014-11-01

    After having recalled the objective of regional radiological observations (establishment of an updated referential of radioactivity levels in some parts of the environment which are typical of the concerned territory), and indicated the three main steps of these observations (definition of a methodology which may differ from one territory to the other, sampling and analysis, assessment of the radiological status of the studied territory), this report presents a methodology which can be applied to big rivers and predominantly agricultural territories. The radiological observations of different areas are reported (Val de Loire, Rhone valley, areas of persistence like mountains, or mining areas). Maps indicate the sampling location and the analysed products (food, soil, plants) and report of the ground or aquatic environment analysis, or available data and sampling strategy are given. The New Caledonia radiological observation is also reported

  3. Applying Multi-Criteria Analysis Methods for Fire Risk Assessment

    Directory of Open Access Journals (Sweden)

    Pushkina Julia

    2015-11-01

    Full Text Available The aim of this paper is to prove the application of multi-criteria analysis methods for optimisation of fire risk identification and assessment process. The object of this research is fire risk and risk assessment. The subject of the research is studying the application of analytic hierarchy process for modelling and influence assessment of various fire risk factors. Results of research conducted by the authors can be used by insurance companies to perform the detailed assessment of fire risks on the object and to calculate a risk extra charge to an insurance premium; by the state supervisory institutions to determine the compliance of a condition of object with requirements of regulations; by real state owners and investors to carry out actions for decrease in degree of fire risks and minimisation of possible losses.

  4. Periorbital facial rejuvenation; applied anatomy and pre-operative assessment

    Directory of Open Access Journals (Sweden)

    Mohsen Bahmani Kashkouli

    2017-09-01

    Conclusion: Static and dynamic aging changes of the periorbital area should be assessed as an eyelid-eyebrow unit paying more attention to the anthropometric landmarks. Assessing the facial asymmetry, performing comprehensive and detailed ocular examination, and asking about patients' expectation are three key elements in this regard. Furthermore, taking standard facial pictures, obtaining special consent form, and finally getting feedback are also indispensable tools toward a better outcome.

  5. Results of survey for assessing awareness level regarding radiological hazards of tobacco smoking

    International Nuclear Information System (INIS)

    Tahir, S. N. A.

    2009-01-01

    Human consumption of tobacco is as old as human history. However, injurious health effects due to tobacco smoking may not be evident to the public at large. This article presents results of a questionnaire based on a survey carried out in the metropolitan city of Lahore of Pakistan with an aim to understand the awareness level of the general population about the radiological hazards associated with tobacco smoking. Some 3600 participants from different educational backgrounds from all segments of the society participated in this survey. Analysis of the data collected concluded that the awareness level of the representative participants regarding the radiological hazards associated with tobacco smoking was alarmingly poor. These results suggest that a nationwide mass media campaign may be launched by the government authorities in Health and Environment departments to enlighten the general public in this respect to avoid tobacco-smoking-associated health risks. (authors)

  6. Assessment of the radiological consequences in case of an emergency on a nuclear installation

    International Nuclear Information System (INIS)

    Manesse, D.; Crabol, B.

    1988-04-01

    The French Institute for Health Physics and Nuclear Safety (IPSN) has, for emergency cases on nuclear installations, an Emergency Technical Centre (Centre Technique de Crise - CTC) to provide the public authorities with the technical analysis of the events and with information concerning possible developments in terms of potential releases and radiological consequences to the environment. The CTC is connected, by a special line, to the French Meteorological Office so as to have access to meteorological parameters and local forecasts on the nuclear site at all times. For atmospheric dispersion and radiological consequences, three methods have been developed: a set of operational graphs (for first aid), a gaussian plume model and a gaussian puff model (SIROCCO); the latter two models are implanted on a VAX 8530 computer (with graphical monitors) reserved for that purpose [fr

  7. The United States Federal Monitoring and Assessment Centre and radiological database management

    International Nuclear Information System (INIS)

    Mueller, P.G.

    1998-01-01

    In the spring of 1979, a series of events occurring at the Three Mile Island Nuclear Power plant near Harrisburg, Pennsylvania, resulted in severe core damage. Recognizing that state resources were insufficient to respond to the first major nuclear power plant emergency in the United States, the State of Pennsylvania asked the Federal Government for assistance. The United States Government undertook the preparation of a plan, which would co-ordinate all federal assets. The Federal Radiological Emergency Response Plan (FRERP) assigned unique responsibilities and authorities for responding to domestic radiological emergencies to each of 12 different federal agencies which form the FRERP. The overall data collection, analysis, and processing procedures within the FRMAC are overviewed. (author)

  8. 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

    The Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter (London Convention 1972) prohibits the disposal at sea of radioactive wastes and other radioactive matter. However natural radionuclides are present in all materials, including natural and inert materials, which can also contain artificial radionuclides from anthropogenic sources such as fallout due to past atmospheric nuclear testing. Therefore, the Contracting Parties to the London Convention 1972 recognized the need to develop definitions and guidelines so that candidate materials (those wastes or other matter not otherwise prohibited from disposal at sea in accordance with Annex I to the Convention) containing less than de minimis levels of specific activity, can be regarded as 'non-radioactive' and may be disposed of at sea subject to the other provisions of the Convention. At the Nineteenth Consultative Meeting in 1997, Contracting Parties to the London Convention 1972 agreed to request the IAEA to develop further the concept of de minimis levels and, in particular, to 'provide guidance for making judgements on whether materials planned to be dumped could be exempted from radiological control or whether a specific assessment was needed' (LC 19/10, paragraph 6.31). This paragraph continues: 'The IAEA would then further be requested to provide guidance to national authorities responsible for conducting specific assessments.' The IAEA presented its advice on de minimis in IAEA-TECDOC-1068, entitled Application of Radiological Exclusion and Exemption Principles to Sea Disposal, to the Twenty-first Consultative Meeting of Contracting Parties to the London Convention 1972 in October 1999. The Contracting Parties accepted these principles and criteria and interpreted them further in the Guidelines for the Application of the De Minimis Concept Under the London Convention 1972 (the Guidelines). At that time, the Contracting Parties asked the IAEA to prepare additional guidance

  9. Evidence-based Practice of Radiology.

    Science.gov (United States)

    Lavelle, Lisa P; Dunne, Ruth M; Carroll, Anne G; Malone, Dermot E

    2015-10-01

    Current health care reform in the United States is producing a shift in radiology practice from the traditional volume-based role of performing and interpreting a large number of examinations to providing a more affordable and higher-quality service centered on patient outcomes, which is described as a value-based approach to the provision of health care services. In the 1990 s, evidence-based medicine was defined as the integration of current best evidence with clinical expertise and patient values. When these methods are applied outside internal medicine, the process is called evidence-based practice (EBP). EBP facilitates understanding, interpretation, and application of the best current evidence into radiology practice, which optimizes patient care. It has been incorporated into "Practice-based Learning and Improvement" and "Systems-based Practice," which are two of the six core resident competencies of the Accreditation Council for Graduate Medical Education and two of the 12 American Board of Radiology milestones for diagnostic radiology. Noninterpretive skills, such as systems-based practice, are also formally assessed in the "Quality and Safety" section of the American Board of Radiology Core and Certifying examinations. This article describes (a) the EBP framework, with particular focus on its relevance to the American Board of Radiology certification and maintenance of certification curricula; (b) how EBP can be integrated into a residency program; and (c) the current value and likely place of EBP in the radiology information technology infrastructure. Online supplemental material is available for this article. © RSNA, 2015.

  10. Aesthetic breast augmentation with hyaluronic acid: imaging findings and implications for radiological assessment

    Directory of Open Access Journals (Sweden)

    Divanei Aparecida Bottaro Criado

    2012-06-01

    Full Text Available New injectable fillers such as hyaluronic acid have recently been employed as a non-surgical alternative to implants such as silicone for aesthetic breast enhancement. Although their utilization is not yet widespread in Brazil, radiologists should be aware of the imaging findings in this context and of the implications of the presence of this filler for the radiological evaluation in the screening for breast cancer.

  11. An assessment of the radiological consequences of accidents in research reactors

    International Nuclear Information System (INIS)

    Ferreira, N.L.D.

    1992-01-01

    This work analyses the radiological consequences of accidents in two types of research reactors: a 5 MWt open pool reactor and a 50 MWt PWR reactor. Two siting cases have been considered: the reactor located near to a large population center and sited in a rural area. The influence of several factors such as source term, meteorological conditions and population distribution have been considered in the present analysis. (author)

  12. An assessment of the radiological consequences of disposal of high-level waste in coastal geologic formations

    International Nuclear Information System (INIS)

    Hill, M.D.; Lawson, G.

    1980-11-01

    This study was carried out with the objectives of assessing the potential radiological consequences of entry of circulating ground-water into a high-level waste repository sited on the coast; and comparing the results with those of previous assessments for a repository sited inland. Mathematical models are used to calculate the rate of release of radioactivity into ground-water by leaching, the rates of migration of radionuclides with ground-water from the repository to the sea and the concentrations of radionuclides in sea-water and sea-food as a function of time. Estimates are made of the peak annual collective doses and collective dose commitments which could be received as a result of sea-food consumption. Since there are considerable uncertainties associated with the values of many of the parameters used in the calculations the broad features of the results are more significant than the numerical values of predicted annual doses and collective dose commitments. The results of the assessment show that the rates of migration of radionuclides with ground-water are of primary importance in determining the radiological impact of ground-water ingress. The implications of this result for selection of coastal sites and allocation of research effort are discussed. The comparison of coastal and inland sites suggest that coastal siting may have substantial advantages in terms of the radiological consequences to the public after disposal and that a significant fraction of available research effort should therefore be directed towards investigation of coastal sites. This study has been carried out under contract to the United Kingdom Atomic Energy Authority, Harwell, on behalf of the Commission of the European Communities. (author)

  13. 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.

  14. 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.

  15. PROBLEMS OF COMPETENCY-BASED ASSESSMENT OF APPLIED QUALIFICATIONS

    Directory of Open Access Journals (Sweden)

    S. A. Efimova

    2017-01-01

    Full Text Available Introduction. The search of the unified tools of competences measurement of vocational training institutions graduates and identification of mechanisms of interrelation of these competences with requirements of professional standards imposed to workers of various levels are brought into focus in the context of formation of National system of qualifications of the Russian Federation, introduction of the Third-generation Federal State Educational Standards and transition of professional education to the modular, and competence-based model of the organization of training. The aim of the article is to justify the content, structure and technology of competency-based assessment, as a set of interrelated activities and regulated procedures performed on the basis of the standardized interdisciplinary evaluation materials. Methodology and research methods. The present investigation is based on systematic-activity and competency-based approaches, analysis, systematization, and generalization. Results. The place of competencies, as a part of educational outcomes of vocational education programs, is justified. Critical analysis of typical methodological solutions that are typical for the modern pedagogical practices of the competency-based assessment is performed. The content and organizational design of the process of competency-based assessment is described. Scientific novelty. The conceptual apparatus of competency-based assessment is supplemented with the «sub-competence» category - component of competence, which retains all of its properties due to human activities. Factors of objects choice and methods of assessment in identifying the professional competences are proved. Practical significance. Results of the study can be used by researchers involved with assessment procedures; methodologists and teachers of professional educational organizations, training institutes, independent centers of the qualifications evaluation for the organization of

  16. Radioactive decay data tables: a handbook of decay data for application to radiation dosimetry and radiological assessments

    International Nuclear Information System (INIS)

    Kocher, D.C.

    1982-01-01

    Reviews compendium containing recommended decay data for approx. 500 radionuclides of interest in nuclear medicine and fusion reactor technology or of potential importance in routine or accidental releases from the nuclear fuel cycle. Primary source of the decay data presented in this handbook is the Evaluated Nuclear Structure Data File (ENSDF), developed and maintained by the US Nuclear Data Network. Topics covered include various radioactive decay processes; evaluation process and standards of ENSDF; tables and computer code MEDLIST used to produce ENSDF tables; radiation dosimetry and radiological assessments; parent-daughter activity ratios wherever the adopted decay data may contain significant uncertainties or errors due to the lack of appropriate experimental data

  17. Radiological controls and worker and public health and safety: An independent safety assessment of Department of Energy nuclear reactor facilities

    International Nuclear Information System (INIS)

    Tew, J.L.; Miles, M.E.; Knuth, D.; Boyd, R.

    1981-02-01

    DOE has formed a Nuclear Facilities Personnel Qualification and Training (NFPQT) Committee to assess the implications of the Report of the President's Commission on the Accident at Three Mile Island that are applicable to DOE's nuclear reactor operations. Thirteen DOE nuclear reactors were reviewed by the Committee. This report was prepared to provide a measure of how the radiological control and environmental practices at the 13 individual DOE reactor facilities measure up to (1) the recommendations contained in the Report of the President's Commission on the Accident at Three Mile Island, (2) the requirements and guidelines contained, and (3) the requirements of the applicable Title and Part of the Code of Federal Regulations

  18. Radiological evaluation of dysphagia

    Energy Technology Data Exchange (ETDEWEB)

    Ott, D.J.; Gelfand, D.W.; Wu, W.C.; Chen, Y.M.

    1986-11-21

    Dysphagia is a common complaint in patients presenting for radiological or endoscopic examination of the esophagus and is usually due to functional or structural abnormalities of the esophageal body or esophagogastric region. The authors review the radiological evaluation of the esophagus and esophagogastric region in patients with esophageal dysphagia and discuss the roentgenographic techniques used, radiological efficacy for common structural disorders, and evaluation of esophageal motor function. Comparison is made with endoscopy in assessing dysphagia, with the conclusion that the radiological examination be used initially in patients with this complaint.

  19. Radiological evaluation of dysphagia

    International Nuclear Information System (INIS)

    Ott, D.J.; Gelfand, D.W.; Wu, W.C.; Chen, Y.M.

    1986-01-01

    Dysphagia is a common complaint in patients presenting for radiological or endoscopic examination of the esophagus and is usually due to functional or structural abnormalities of the esophageal body or esophagogastric region. The authors review the radiological evaluation of the esophagus and esophagogastric region in patients with esophageal dysphagia and discuss the roentgenographic techniques used, radiological efficacy for common structural disorders, and evaluation of esophageal motor function. Comparison is made with endoscopy in assessing dysphagia, with the conclusion that the radiological examination be used initially in patients with this complaint

  20. Radioactivity in the environment. A summary and radiological assessment of the Environment Agency's monitoring programmes; report for 1997

    International Nuclear Information System (INIS)

    1997-01-01

    The Radioactive Substances Act 1993 provides for controls to be exercised over the keeping and use of radioactive materials and, in particular, on the accumulation and disposal of radioactive wastes. The Environment Agency is responsible for administration and enforcement of the Act in England and Wales. In support of these regulatory functions and as part of the UK Government's arrangements for providing information to the European Commission under the Euratom Treaty, the Agency commissions independent monitoring of radioactive waste disposals and their impact on the environment, and monitoring of radioactivity in air, rainwater and drinking water sources. This report presents the data from these monitoring programmes and provides a commentary on their radiological significance. It includes assessments of radiation exposure of members of the public for compliance with the annual dose limit recommended by the International Commission on Radiological Protection. Concentrations of radioactivity in water are also assessed in relation to the guidelines on drinking water quality recommended by the World Health Organisation. This report for 1997 is one of an annual series published by the Agency. It is being distributed to local authorities as part of the arrangements under the Radioactive Substances Act 1993 for provision of access to environmental information. The monitoring programmes and preparation of this report are managed by the Agency's National Compliance Assessment Service. (author)

  1. Assessment of Physical Activity by Applying IPAQ Questionnaire

    Science.gov (United States)

    Biernat, Elzbieta; Stupnicki, Romuald; Lebiedzinski, Bartlomiej; Janczewska, Lidia

    2008-01-01

    Study aim: To assess the suitability of the short 7-day IPAQ (self-completed) adapted to Polish population. Material and methods: Two surveys were conducted in 2005 on 296 random subjects (aged 20-60 years) from Warsaw and the Mazowiecki region. From these, 54 men and 79 women were requested to fill questionnaires, and 70 men and 93 women, were…

  2. Fried frailty phenotype assessment components as applied to geriatric inpatients

    Directory of Open Access Journals (Sweden)

    Bieniek J

    2016-04-01

    Full Text Available Joanna Bieniek, Krzysztof Wilczynski, Jan Szewieczek Department of Geriatrics, School of Health Sciences in Katowice, Medical University of Silesia, Katowice, Poland Background: Management of geriatric patients would be simplified if a universally accepted definition of frailty for clinical use was defined. Among definitions of frailty, Fried frailty phenotype criteria constitute a common reference frame for many geriatric studies. However, this reference frame has been tested primarily in elderly patients presenting with relatively good health status. Objective: The aim of this article was to assess the usefulness and limitations of Fried frailty phenotype criteria in geriatric inpatients, characterized by comorbidity and functional impairments, and to estimate the frailty phenotype prevalence in this group. Patients and methods: Five hundred consecutive patients of the university hospital subacute geriatric ward, aged 79.0±8.4 years (67% women and 33% men, participated in this cross-sectional study. Comprehensive geriatric assessment and Fried frailty phenotype component evaluation were performed in all patients. Results: Multimorbidity (6.0±2.8 diseases characterized our study group, with a wide range of clinical conditions and functional states (Barthel Index of Activities of Daily Living 72.2±28.2 and Mini-Mental State Examination 23.6±7.1 scores. All five Fried frailty components were assessed in 65% of patients (95% confidence interval [CI] =60.8–69.2 (diagnostic group. One or more components were not feasible to be assessed in 35% of the remaining patients (nondiagnostic group because of lack of past patient’s body mass control and/or cognitive or physical impairment. Patients from the nondiagnostic group, as compared to patients from the diagnostic group, presented with more advanced age, higher prevalence of dementia, lower prevalence of hypertension, lower systolic and diastolic blood pressure, body mass index, Mini

  3. Applying real options analysis to assess cleaner energy development strategies

    International Nuclear Information System (INIS)

    Cheng, Ching-Tsung; Lo, Shang-Lien; Lin, Tyrone T.

    2011-01-01

    The energy industry, accounts for the largest portion of CO 2 emissions, is facing the issue of compliance with the national clean energy policy. The methodology for evaluating the energy mix policy is crucial because of the characteristics of lead time embedded with the power generation facilities investment and the uncertainty of future electricity demand. In this paper, a modified binomial model based on sequential compound options, which may account for the lead time and uncertainty as a whole is established, and a numerical example on evaluating the optional strategies and the strategic value of the cleaner energy policy is also presented. It is found that the optimal decision at some nodes in the binomial tree is path dependent, which is different from the standard sequential compound option model with lead time or time lag concept. The proposed modified binomial sequential compound real options model can be generalized and extensively applied to solve the general decision problems that deal with the long lead time of many government policies as well as capital intensive investments. - Highlights: → Introducing a flexible strategic management approach for government policy making. → Developing a modified binomial real options model based on sequential compound options. → Proposing an innovative model for managing the long term policy with lead time. → Applying to evaluate the options of various scenarios of cleaner energy strategies.

  4. Fiscal Feasibility Assessment Applied to Transport Infrastructure Projects

    Energy Technology Data Exchange (ETDEWEB)

    Guilherme de Aragão, J.J.; Santos Fontes Pereira, L. dos; Yamashita, Y.; Brandão, R.

    2016-07-01

    The demand for transport infrastructure investment is a latent issue for several countries, mainly for developing countries. However, investments in major logistics projects should be carefully evaluated, in order that their deployment induces development without endangering fiscal sustainability by excessive public indebtedness. Fiscal accounting practices used currently in the feasibility studies of transport infrastructures in Brazil are very limited, as they do not consider indirect and induced effects of the infrastructure investment in the fiscal evaluation. In addition, the corresponding influence area has not an established delimitation method. The aim of the present paper is to develop a model for calculating economic and fiscal impacts of transport infrastructure investment projects that includes the direct, indirect and induced effects within a reference area do be determined. First, different project assessment guides in Brazil and abroad are examined with a special focus on the assessment of economic and fiscal impacts of the projects. Based on the assessment experience and on the definition of the fiscal balance of an infrastructure project, the next step sets up a framework for the calculation of the impacts, using more simplified data. (Author)

  5. The Ability of the United States Federal Radiological Monitoring and Assessment Center to Collect and Disseminate Environmental Measurements during Radiological Emergencies

    International Nuclear Information System (INIS)

    Marianno, Craig; Essex, James

    2007-01-01

    The Federal Radiological Monitoring and Assessment Center (FRMAC) is the United States response organization for radiological emergencies. The FRMAC is structured as an operations center and employs the combined resources of several federal agencies to respond to any disaster resulting in the release of radioactivity. The mission of the FRMAC is to support state and local authorities in the gathering of environmental data using an array of survey equipment ranging from alpha probes, beta/gamma probes, and high-purity germanium (HPGe) spectroscopy to the gathering of physical samples. Once collected, the data are projected on maps to assist public officials make protective action decisions. In addition to the accumulation of data, it is the legal obligation of the FRMAC to keep archival records of all data points and their actions. During an event, it is conceivable that hundreds to thousands of sample points will be recorded over a relatively short time. It is in the interest of the federal government and public that the information collected be put to the best use as fast as possible. Toward this end, the Remote Sensing Laboratory, working under the direction of the United States Department of Energy's National Nuclear Security Administration, is investigating the use of several technologies that will accelerate data flow from field teams to the FRMAC and, finally, distribution of data to decision makers and the public. Not only can finished data products be viewed through the internet, but the actual collection of data via 'real-time' telemetry can be viewed using this same method. Data from the field will be transferred directly to the FRMAC using the MCPD (multi-path communication device). This base station receives the survey information from the field teams via Bluetooth and instantly investigates the best communication pathway to transfer data to the FRMAC. Possible paths include standalone radio, commercial cellular networks (GPRS and CDMA) and satellite

  6. PARATI: A program for radiological assessment after radioactive contamination of urban areas

    International Nuclear Information System (INIS)

    Rochedo, E.; Conti, L.F.; Paretzke, H.G.

    2000-01-01

    A dynamic model aimed on the assessment of the long-term consequences of an accidental contamination of urban environments has been developed. The model was designed to assess the radiation exposure, as a function of time, of the different kinds of people that uses the contaminated environment, the relative contribution of each exposure pathway to simulate the application of countermeasures and its effects on the reduction of surfaces contamination and on the exposure of the individuals and of the population. The model is an empirical one, mainly based on environmental data gathered after the Chernobyl and Goiania accidents, and takes into account climatic and population habits characteristics of tropical areas. The model was applied here to a contamination with the radionuclide 137 Cs but can be easily adapted to other nuclides by changes on parameter values. An analysis of the variabilities associated to the model outputs regarding population habits, different kinds of urban environment and parameters uncertainty has shown that the main source of uncertainty on model predictions is associated to a correct knowledge of population characteristics, its habits and uses of the contaminated environment. (author)

  7. 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

  8. Statistical analysis applied to safety culture self-assessment

    International Nuclear Information System (INIS)

    Macedo Soares, P.P.

    2002-01-01

    Interviews and opinion surveys are instruments used to assess the safety culture in an organization as part of the Safety Culture Enhancement Programme. Specific statistical tools are used to analyse the survey results. This paper presents an example of an opinion survey with the corresponding application of the statistical analysis and the conclusions obtained. Survey validation, Frequency statistics, Kolmogorov-Smirnov non-parametric test, Student (T-test) and ANOVA means comparison tests and LSD post-hoc multiple comparison test, are discussed. (author)

  9. An assessment of the terrorist threat to use a nuclear or radiological device in an attack

    Energy Technology Data Exchange (ETDEWEB)

    Kingshott, B.F. [Grand Valley State University, 275C DeVos Center, 401 West Fulton Street, Grand Rapids, MI 49504 (United States)]. E-mail: kingshob@gvsu.edu

    2006-07-01

    This paper will discuss terrorism from the perspective of a terrorist organisation acquiring nuclear material to build weapons and how security of radiological material world wide will minimise the risk of such devices being used. It will discuss the need to improve security at nuclear waste processing and storage sites and the adequacy of current security. It will also discuss the phenomenon of suicide attacks by the bomb carriers and the role of the media in informing and educating the general public of the consequences should such a device containing nuclear material be detonated. (author)

  10. Comparison of dynamic ultrasound and stress radiology for assessment of inferior glenohumeral laxity in asymptomatic shoulders

    International Nuclear Information System (INIS)

    Cheng, S.C.; Wallace, W.A.; Hulse, D.; Fairbairn, K.J.; Clarke, M.

    2008-01-01

    To determine the level of agreement between dynamic ultrasound imaging and stress radiography used for the measurement of inferior glenohumeral laxity in asymptomatic shoulders, and to determine the repeatability of the dynamic ultrasound technique. Using a custom-made stress device to apply an inferior displacement force of 90 N, we assessed 20 asymptomatic male subjects for inferior glenohumeral laxity, using stress radiography and dynamic ultrasound. Paired differences between the two methods were evaluated by the 95% limits of agreement method. At a separate session, 19 subjects had inferior glenohumeral laxity assessed by two observers, using dynamic ultrasound. Inter- and intra-observer repeatability was determined for the ultrasound technique. The mean [± standard deviation (SD)] inferior translation was 4.7 ± 4.1 mm by stress radiography and 4.4 ± 2.3 mm by dynamic ultrasound. The 95% limits of agreement showed good agreement between the two methods. The paired difference between the two measurement methods varied with the magnitude of the measurement (P < 0.001). Intra-observer repeatability of dynamic ultrasound was determined by the use of intra-class correlation coefficients and was 0.94 and 0.89 for the two investigators. Inter-observer repeatability was 0.85. The standard error of the measurement was 0.60 mm and 0.66 mm, for repeated measurements by the two investigators, and 0.85 mm between investigators. Repeatability coefficients demonstrated excellent consistency of measurement between sessions and good consistency between observers. Dynamic ultrasound is a valid and reproducible method for the assessment and quantification of inferior glenohumeral laxity. (orig.)

  11. Videofluoroscopic assessment of dysphagia: A questionnaire survey of protocols, roles and responsibilities of radiology and speech and language therapy personnel

    International Nuclear Information System (INIS)

    Power, Maxine; Laasch, Hans-Ulrich; Kasthuri, Ram S.; Nicholson, David A.; Hamdy, Shaheen

    2006-01-01

    Videofluoroscopy (VF) is the 'gold standard' assessment for oropharyngeal dysphagia and radiographers are beginning to direct this examination independently, yet little is known about the roles and responsibilities of the core professions of radiology and speech and language therapy and their practice in this examination. Aim: To evaluate VF practice and identify the roles and responsibilities of radiology and speech and language therapy personnel. Materials and methods: A questionnaire was developed and distributed to speech and language therapists (SALT) and radiologists via national special interest networks. Information regarding protocols, test materials, supervision, radiation protection and training was obtained. Results: One hundred and thirteen questionnaires were completed, 83% of respondents had more than 5 years service. Most were carrying out VF on an 'ad hoc' basis with only 32% participating in more than 6 assessments per month. There was no consensus on protocol and 41% chose to thicken barium solutions by adding more barium sulphate powder, potentially predisposing patients to complications. Over 50% of SALTs had received one day post-graduate training in VF, whereas, only one radiologist had specific VF training. Conclusion: Despite its importance in determining the feeding route for patients, VF is carried out infrequently by most clinicians and protocols vary widely. Moreover, intra- and inter-disciplinary training and supervision is minimal. More work is needed to develop standard guidelines, to improve the quality of the examination and its reproducibility

  12. Residual radioactivity investigation and radiological assessments for self-disposal of concrete waste in nuclear fuel processing facility

    International Nuclear Information System (INIS)

    Seol, Jeung Gun; Ryu, Jae Bong; Cho, Suk Ju; Yoo, Sung Hyun; Song, Jung Ho; Baek, Hoon; Kim, Seong Hwan; Shin, Jin Seong; Park, Hyun Kyoun

    2007-01-01

    In this study, domestic regulatory requirement was investigated for self-disposal of concrete waste from nuclear fuel processing facility. And after self-disposal as landfill or recycling/reuse, the exposure dose was evaluated by RESRAD Ver. 6.3 and RESRAD BUILD Ver. 3.3 computing code for radiological assessments of the general public. Derived clearance level by the result of assessments for the exposure dose of the general public is 0.1071Bq/g (3.5% enriched uranium) for landfill and 0.05515 Bq/cm 2 (5% enriched uranium) for recycling/reuse respectively. Also, residual radioactivity of concrete waste after decontamination was investigated in this study. The result of surface activity is 0.01Bq/cm 2 for emitter and the result of radionuclide analysis for taken concrete samples from surface of concrete waste is 0.0297Bq/g for concentration of 238 U, below 2w/o for enrichment of 235 U and 0.0089Bq/g for artificial contamination of 238 U respectively. Therefore, radiological hazard of concrete waste by self-disposal as landfill and recycling/reuse is below clearance level to comply with clearance criterion provided for Notice No. 2001-30 of the MOST and Korea Atomic Energy Act

  13. Quality assessment of butter cookies applying multispectral imaging

    Science.gov (United States)

    Andresen, Mette S; Dissing, Bjørn S; Løje, Hanne

    2013-01-01

    A method for characterization of butter cookie quality by assessing the surface browning and water content using multispectral images is presented. Based on evaluations of the browning of butter cookies, cookies were manually divided into groups. From this categorization, reference values were calculated for a statistical prediction model correlating multispectral images with a browning score. The browning score is calculated as a function of oven temperature and baking time. It is presented as a quadratic response surface. The investigated process window was the intervals 4–16 min and 160–200°C in a forced convection electrically heated oven. In addition to the browning score, a model for predicting the average water content based on the same images is presented. This shows how multispectral images of butter cookies may be used for the assessment of different quality parameters. Statistical analysis showed that the most significant wavelengths for browning predictions were in the interval 400–700 nm and the wavelengths significant for water prediction were primarily located in the near-infrared spectrum. The water prediction model was found to correctly estimate the average water content with an absolute error of 0.22%. From the images it was also possible to follow the browning and drying propagation from the cookie edge toward the center. PMID:24804036

  14. Assessment of natural radioactivity and radiological hazards in building materials used in the Tiruvannamalai District, Tamilnadu, India, using a statistical approach

    Directory of Open Access Journals (Sweden)

    Y. Raghu

    2017-07-01

    Full Text Available One-hundred-fifty-one samples of six types of building materials were collected from different locations of the Tiruvannamalai District, Tamilnadu, and were analyzed using a gamma ray spectroscopy system. From the results, the highest values observed in the specific activities of 226Ra, 232Th and 40K were 116.1 (soil 106.67 (sand and 527.533 (tiles in Bq kg−1, while the lowest values observed in the specific activities of the same radionuclides were 35.73, 37.75 and 159.83 for cement in Bq kg−1, respectively. The potential radiological hazards were assessed by calculating the radium equivalent activity (Raeq, the indoor absorbed gamma dose rate (DR, the annual effective dose rate (HR, the activity utilization index (I, the alpha index (Iα, the gamma index (Iγ, and the external hazard (Hex and internal hazard (Hin indices. The estimated mean value of the absorbed dose rate of 148.35 nGy h−1 is slightly higher than the world average value of 84 nGy h−1, and the annual effective dose in the studied samples is 0.1824 mSv y−1, which is lower than the recommended limit. Multivariate statistical methods are applied to determine the existing relationship between radionuclides and radiological health hazard parameters and to identify the maximum contribution of radionuclide in radioactivity. The values of the hazard indices were below the recommended levels; therefore, it is concluded that the buildings constructed from such materials are safe for the inhabitants. The findings from this research will be useful to assess the radiation hazards of building materials in humans.

  15. Brachytherapy, diagnostic radiology, mammographic radiology and ophthalmic applicators. An assessment of current and future needs in the UK and the role of NPL

    International Nuclear Information System (INIS)

    Angliss, R.; Bass, G.; Sander, T.

    2001-01-01

    Several UK hospitals were visited by NPL staff to discuss the current practises and future developments in brachytherapy, diagnostic and mammographic radiology and ophthalmic applicators. The results of the discussions are presented here, including NPL's role in each of these areas is discussed. (author)

  16. Life cycle assessment applied to nanomaterials in solid waste management

    DEFF Research Database (Denmark)

    Laurent, Alexis

    While the generation of solid waste is globally increasing, much effort is concentrated to minimise the environmental impacts related to their management. With respect to nanoproducts (products containing nanomaterials), a growing amount of ‘nanowaste’ can be expected to enter the waste streams...... on specific waste types and waste management systems, all primarily reflecting situations in economicallydeveloped countries. At the same time, methodological practice was found in many studies not to be compliant with current reference guidance, such as the ISO standards and the ILCD Handbook. Likewise......, thus potentially posing problems on human health, e.g. through occupational exposure to engineered nanoparticles. In that setting, through its holistic quantification of environmental impacts, life cycle assessment (LCA) can be a useful decisionsupport tool for managing environmental sustainability...

  17. Radiologic assessment of the outcome of Keller and Brandes arthroplasty for hallux rigidus

    International Nuclear Information System (INIS)

    Breitenseher, M.J.; Toma, C.D.; Gottsauner-Wolf, F.; Imhof, H.

    1996-01-01

    The aim of this study was to evaluate the pre- and postoperative radiographic findings of hallux rigidus treated with Keller and Brandes arthroplasty to determine the radiographic outcome and to identify a prognostic marker. 83 patients with a total of 121 cases of hallux rigidus operated using Keller and Brandes arthroplasty were followed up (mean 9.7 y). A comparison of the pre- and postoperative radiographs, the clinical and subjective findings was predicated on a five point scale: 1. Percentage of proximal phalanx resected ( 50%), 2. joint space, 3. ratio of the length of the first and second metatarsals, 4. first intermetatarsal angle, and 5. hallux valgus angle. In the patient group which had 33-50% of the proximal phalanx excised (n=67. 55%) the highest patient satisfaction was observed (96%). If resection of the proximal phalanx exceeded 50% (n=13. 11%), non physiologic dorsiflexion of the toe occurred and patients were unsatisfied (62%). Excision of less than 33% of the hallux (n=41. 34%) was associated with a recurrent hallux rigidus. No other evaluated radiological parameter proved to be of significance. The most important radiological parameter in the evaluation of the outcome of Keller and Brandes arthroplasty as the percentage of the proximal phalanx which had ben excised. (orig.) [de

  18. Soil depth profiles and radiological assessment of natural radionuclides in forest ecosystem

    International Nuclear Information System (INIS)

    Manigandan, P.K.; Chandar Shekar, B.

    2017-01-01

    We measured the distribution of three naturally occurring radionuclides, "2"3"8U, "2"3"2Th, and "4"0K, in soil samples collected from a rainforest in the Western Ghats of India. For each surface sample, we calculated average activity concentration, outdoor terrestrial γ dose rate, annual effective dose equivalent (AEDE), and radiation hazard index. The activity concentrations of surface samples were randomly distributed over space, but differed slightly with different soil depths. The concentration of "2"3"2Th and the average terrestrial γ dose rates were slightly higher than the world averages, so slightly high γ radiation appears to be a general characteristic of the Western Ghats. However, all radiological hazard indices were within the limits proposed by the International Commission on Radiological Protection. The results reported here indicate that, except for "2"3"2Th, the naturally occurring radionuclides in the forest soils of the Western Ghats were within the ranges specified by United Nations Scientific Committee on the Effects of Atomic Radiation for undisturbed virgin soils.

  19. 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

  20. Aortic intramural hematoma : assessment of clinical and radiological features in comparison to acute aortic dissection

    International Nuclear Information System (INIS)

    Yoon, Kwon Ha; Hwang, Jae Cheol; Lee, Jin Seong; Kang, Duk Hyun; Song, Jae Kwan; Song, Koun Sik; Lim, Tae Hwan

    1996-01-01

    To compare the clinical and radiological features of aortic intramural hematoma(IMH) to those of acute aortic dissection(AD). We analyzed the clinical and radiological features of 12 patients with aortic IMH and 43 patients with acute AD. In aortic IMH, the diagnoses were made by means of both CT and transesophageal echocardiography(TEE) and included two surgically proven cases. In acute AD, the diagnoses were made by means of CT and TEE and included 21 surgically proven cases. We compared patients ages, etiologies, the extent of the disease, the presence or absence of aortic branch involvement, complications, and outcomes. Aortic IMH tended to develop in older patients (67.8±7.9 vs. 50.4±13.4, P .05). In aortic IMH, there was no involvement of aortic branches, whereas in acute AD, 14(33%) patients showed involvement of one or more aortic branches. Complications of aortic IMH included pericardial effusion (n=2) and pleural effusion (n=4);in acute AD, pericardial effusion (n=7), pleural effusion (n=4), aortic insufficiency (n=8), cerebral infarction (n=3), renal infarction (n=4) and spinal infarction (n=1) were seen. There was one (8%) death due to aortic IMH and ten (23%) deaths due to acute AD (p<.01). Aortic IMH is characterized by its occurrence in older patients with hypertension, a less frequent incidence of complications, and a more favorable outcome than acute AD

  1. 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.

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