WorldWideScience

Sample records for radiological consequence analysis

  1. 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

  2. Evaluation system for the analysis of the radiological consequences (RASCAL)

    International Nuclear Information System (INIS)

    Miguel Martinez, M. J. de

    2011-01-01

    The code currently employed by the Spanish Nuclear power is the IRDAM (Interactive Rapid Dose Assessment Model). This code will now be replaced by the RASCAL (Radiological Assessment System for Consequence Analysis) version 4.0. This is a significant improvement in dose calculation for escapes to the atmosphere for radioactive emergencies. The main objective is to highlight the most significant changes introduced in the RASCAL when performing these dose estimates.

  3. Radiological consequence analysis of a repository for radioactive waste

    International Nuclear Information System (INIS)

    Fitzpatrick, J.; Buchheim, B.; Hoop, F.J.

    1982-01-01

    One of the methods under consideration for the disposal of radioactive wastes is emplacement in a repository within deep, continental formations. This paper presents the experience gained in developing a methodology to make an assessment of the radiological consequences both for normal operation and for possible accident situations for a specific repository design in a salt dome at Gorleben in Germany , designed to accommodate all categories of radioactive waste. Radionuclide release scenarios were derived from a systematic analysis of the facility design and proposed operational procedure. Where necessary simple numerical models for such topics as direct radiation exposure from waste containers, release and transport of radionuclides, radiolysis, heat transfer, creep and impact were developed to give a first estimate of the radiological consequences due to radionuclide releases. (author)

  4. Radiological consequence analysis with HEU and LEU fuels

    Energy Technology Data Exchange (ETDEWEB)

    Woodruff, W.L.; Warinner, D.K.; Matos, J.E.

    1984-01-01

    A model for estimating the radiological consequences from a hypothetical accident in HEU and LEU fueled research and test reactors is presented. Simple hand calculations based on fission product yield table inventories and non-site specific dispersion data may be adequate in many cases. However, more detailed inventories and site specific data on meteorological conditions and release rates and heights can result in substantial reductions in the dose estimates. LEU fuel gives essentially the same doses as HEU fuel. The plutonium buildup in the LEU fuel does not significantly increase the radiological consequences. The dose to the thyroid is the limiting dose. 10 references, 3 figures, 7 tables.

  5. Radiological consequence analysis with HEU and LEU fuels

    International Nuclear Information System (INIS)

    Woodruff, W.L.; Warinner, D.K.; Matos, J.E.

    1984-01-01

    A model for estimating the radiological consequences from a hypothetical accident in HEU and LEU fueled research and test reactors is presented. Simple hand calculations based on fission product yield table inventories and non-site specific dispersion data may be adequate in many cases. However, more detailed inventories and site specific data on meteorological conditions and release rates and heights can result in substantial reductions in the dose estimates. LEU fuel gives essentially the same doses as HEU fuel. The plutonium buildup in the LEU fuel does not significantly increase the radiological consequences. The dose to the thyroid is the limiting dose. 10 references, 3 figures, 7 tables

  6. A radiological consequence analysis with HEU and LEU fuels

    International Nuclear Information System (INIS)

    Woodruff, W.L.; Warinner, D.K.; Matos, J.E.

    1985-01-01

    A model for estimating the radiological consequences from a hypothetical accident in HEU and LEU fueled research and test reactors is presented. Simple hand calculations based on fission product yield table inventories and nonsite specific dispersion data may be adequate in many cases. However, more detailed inventories and site specific data on meteorological conditions and release rates and heights can result in substantial reductions in the dose estimates. LEU fuel gives essentially the same doses as HEU fuel. The plutonium buildup in the LEU fuel does not significantly increase the radiological consequences. The dose to the thyroid is the limiting dose. (author)

  7. Radiological Consequences Analysis for Abnormal Condition on NPPs 1000 MWe by Using Radcon Model

    International Nuclear Information System (INIS)

    Pande Mande Udiyani; Sri Kuntjoro

    2009-01-01

    The operation of NPPs (Nuclear Power Plants) in Indonesia to anticipates rare of energy will generate various challenges, especially about NPPs safety. So installation organizer of nuclear must provide scientific argument to safety NPPs, one of them is by providing document of safety analysis. Calculation of radiological consequences after abnormal condition applies on generic PWR-1000 power reactor. Calculation is done by using program package RadCon (Radiological Consequences Model), with postulate condition is based on DBA (Design Basis Accident). Calculation of dispersion of radionuclide concentration is using PC-COSYMA as input data for RadCon. Simulation for radiological consequences analysis uses by site data sample. Analysis result shows that maximum receiving of internal - externals radiological consequence for short term and long-term below 1 km radius area is below the limit acceptably effective dose for a member of the public as a result of an accident which should not exceed 5 mSv (ICRP 1990). (author)

  8. Offsite radiological consequence analysis for the bounding aircraft crash accident

    International Nuclear Information System (INIS)

    OBERG, B.D.

    2003-01-01

    The purpose of this calculation note is to quantitatively analyze a bounding aircraft crash accident for comparison to the DOE-STD-3009-94, ''Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses'', Appendix A, Evaluation Guideline of 25 rem. The potential of aircraft impacting a facility was evaluated using the approach given in DOE-STD-3014-96, ''Accident Analysis for Aircraft Crash into Hazardous Facilities''. The following aircraft crash FR-equencies were determined for the Tank Farms in RPP-11736, ''Assessment Of Aircraft Crash FR-equency For The Hanford Site 200 Area Tank Farms'': (1) The total aircraft crash FR-equency is ''extremely unlikely.'' (2) The general aviation crash FR-equency is ''extremely unlikely.'' (3) The helicopter crash FR-equency is ''beyond extremely unlikely.'' (4) For the Hanford Site 200 Areas, other aircraft type, commercial or military, each above ground facility, and any other type of underground facility is ''beyond extremely unlikely.'' As the potential of aircraft crash into the 200 Area tank farms is more FR-equent than ''beyond extremely unlikely,'' consequence analysis of the aircraft crash is required

  9. Analysis of radiological consequences in a typical BWR with a mark-II containment

    International Nuclear Information System (INIS)

    Funayama, Kyoko; Kajimoto, Mitsuhiro

    2003-01-01

    INS/NUPEC in Japan has been carrying out the Level 3 PSA program. In the program, the MACCS2 code has been extensively applied to analyze radiological consequences for typical BWR and PWR plants in Japan. The present study deals with analysis of effects of the AMs, which were implemented by industries, on radiological consequence for a typical BWR with a Mark-II containment. In the present study, source terms and their frequencies of source terms were used based on results of Level 2 PSA taking into account AM countermeasures. Radiological consequences were presented with dose risks (Sv/ry), which were multiplied doses (Sv) by containment damage frequencies (/ry), and timing of radionuclides release to the environment. The results of the present study indicated that the dose risks became negligible in most cases taking AM countermeasures and evacuations. (author)

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

    International Nuclear Information System (INIS)

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

    1988-01-01

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

  11. Radiological consequences of radioactive effluents

    International Nuclear Information System (INIS)

    Clarke, R.H.

    1979-01-01

    A study of the differential radiological impact of the nuclear fuel cycle with and without plutonium recycle is being undertaken jointly by the National Radiological Protection Board and the Commissariat a l'Energie Atomique (CEA). A summary is given of the development of the methodology detailed in their first report to the Commission of the European Communities (CEC) (NRPB/CEA, A methodology for evaluating the radiological consequences of radioactive effluents released in normal operations. Luxembourg, CEC Doc. V/3011/75 EN (1979)). The Collective Effective Dose Equivalent Commitment was used in an attempt to assess the total health detriment. The application of the methodology within particular member states of the European Community has been discussed at seminars. Sensitivity analysis can identify the more important parameters for improving the accuracy of the assessment. (UK)

  12. Radiological consequence analysis for upgradation of Pakistan Research Reactor-1 from 9 to 10 MW

    International Nuclear Information System (INIS)

    Khan, L.A.; Raza, S.S.

    1993-12-01

    Radiological consequence analysis has been carried out for upgradation of PARR-I from 9 to 10 MW. A hypothetical loss of coolant accident resulting in core meltdown and release of fission products to the atmosphere has been analyzed. Whole body and thyroid doses have been calculated as a function of time and distance from the containment building. Based on these dose estimates, boundaries of exclusion and low population zones are assessed. (author)

  13. Some issues on radiological consequences analysis in site selection for nuclear power stations

    International Nuclear Information System (INIS)

    Chen Xiaoqiu; Yue Huiguo

    2006-01-01

    The three considerations, Site safety and environmental protection and emergency preparedness, are the focus of attention in the evaluation of the suitability of a site for nuclear power station. This paper summarized the basic regulatory requirements for the siting of nuclear power station, described the existing problems on radiological consequences analyses during the siting stage and discussed the is- sues that need to concern in the reviewing of the radiological consequences analyses in the siting appraisal stage. (authors)

  14. RASCAL 4.l: evaluation system for the analysis of the radiological consequences

    International Nuclear Information System (INIS)

    Miguel, I. de; Gomez-Arguello, B.

    2012-01-01

    Recently the Spanish Nuclear Safety Council (CSN) has promoted the replacement of the code used in the Spanish Nuclear Power Plants to estimate potential and actual doses due to atmospheric releases. IRDAM Code (interactive Rapid Dose Assessment Model, 1983) by RASCAL Code version 4.1 (Radiological Assessment System for consequence Analysis). This code was developed by the NRC (Nuclear Regulatory Commission) to evaluate releases from nuclear power plants, spent fuel storage pools and casks, fuel cycle facilities and radioactive material handling facilities. RASCAL was officially requested to the Spanish nuclear power plants in February 1st, 2012, and it can be used for external dose assessment and to evaluate the recommended protective action for the public in a specific situation (sheltering, prophylaxis, evacuation, etc.). (Author)

  15. Health effects models for off-site radiological consequence analysis on nuclear reactor accidents (II)

    Energy Technology Data Exchange (ETDEWEB)

    Homma, Toshimitsu [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Takahashi, Tomoyuki [Kyoto Univ., Kumatori, Osaka (Japan). Research Reactor Inst; Yonehara, Hidenori [National Inst. of Radiological Sciences, Chiba (Japan)] [eds.

    2000-12-01

    This report is a revision of JAERI-M 91-005, 'Health Effects Models for Off-Site Radiological Consequence Analysis of Nuclear Reactor Accidents'. This revision provides a review of two revisions of NUREG/CR-4214 reports by the U.S. Nuclear Regulatory Commission which is the basis of the JAERI health effects models and other several recent reports that may impact the health effects models by international organizations. The major changes to the first version of the JAERI health effects models and the recommended parameters in this report are for late somatic effects. These changes reflect recent changes in cancer risk factors that have come from longer followup and revised dosimetry in major studies on the Japanese A-bomb survivors. This report also provides suggestions about future revisions of computational aspects on health effects models. (author)

  16. Health effects models for off-site radiological consequence analysis on nuclear reactor accidents (II)

    International Nuclear Information System (INIS)

    Homma, Toshimitsu

    2000-12-01

    This report is a revision of JAERI-M 91-005, 'Health Effects Models for Off-Site Radiological Consequence Analysis of Nuclear Reactor Accidents'. This revision provides a review of two revisions of NUREG/CR-4214 reports by the U.S. Nuclear Regulatory Commission which is the basis of the JAERI health effects models and other several recent reports that may impact the health effects models by international organizations. The major changes to the first version of the JAERI health effects models and the recommended parameters in this report are for late somatic effects. These changes reflect recent changes in cancer risk factors that have come from longer followup and revised dosimetry in major studies on the Japanese A-bomb survivors. This report also provides suggestions about future revisions of computational aspects on health effects models. (author)

  17. Mission Analysis for Using Preventive Radiological/Nuclear Detection Equipment for Consequence Management

    Energy Technology Data Exchange (ETDEWEB)

    Buddemeier, Brooke R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Wood-Zika, Annmarie R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Haynes, Daniel [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Klemic, Gladys A. [US Dept. of Homeland Security National Urban Security Technology Lab., Manhattan, NY (United States); Musolino, Stephen V. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2017-09-01

    The overall objective of this project is to research, evaluate, and test first responder preventive radiological/nuclear detection (PRND) equipment to provide state and local agencies with scientific guidance on how to effectively use this equipment for response after a radiological/nuclear release or detonation. While the equipment being tested in this effort has been specifically designed by technology manufacturers and purchased by responders for preventive detection and source interdiction operations, the fleet of PRND equipment can help fill critical needs for radiological instrumentation should a consequence management (CM) response take place, as it is currently the most widely available and fielded radiological instrumentation by state and local agencies. This effort will provide scientific guidance on the most effective way to utilize this class of equipment for consequence management missions. Gaining a better understanding of how PRND equipment can operate and perform for these missions will allow for recommendations on the tactical approach responders can use for consequence management operations. PRND equipment has been placed into service by federal, state, and local agencies throughout the nation. If the equipment capability and limitations are taken into account, this large inventory can be leveraged to support the emergency response in the aftermath of a radiological or nuclear event. With several hundred makes and models of PRND equipment, often with significantly different detection capabilities that do not align with their nominal PRND equipment type, development of a streamlined categorization scheme with respect to consequence management missions was the first step to identifying safe and effective uses of PRND equipment for radiological/nuclear incident response.

  18. Degraded core accidents for the Sizewell PWR A sensitivity analysis of the radiological consequences

    CERN Document Server

    Kelly, G N; Clarke, R H; Ferguson, L; Haywood, S M; Hemming, C R; Jones, J A

    1982-01-01

    The radiological impact of degraded core accidents postulated for the Sizewell PWR was assessed in an earlier study. In this report the sensitivity of the predicted consequences to variation in the values of a number of important parameters is investigated for one of the postulated accidental releases. The parameters subjected to sensitivity analyses are the dose-mortality relationship for bone marrow irradiation, the energy content of the release, the warning time before the release to the environment, and the dry deposition velocity for airborne material. These parameters were identified as among the more important in determining the uncertainty in the results obtained in the initial study. With a few exceptions the predicted consequences were found to be not very sensitive to the parameter values investigated, the range of variation in the consequences for the limiting values of each parameter rarely exceeded a factor of a few and in many cases was considerably less. The conclusions reached are, however, p...

  19. Radiological consequence analysis. Report on the work package 10. Preliminary safety analysis for the site Gorleben; Radiologische Konsequenzanalyse. Bericht zum Arbeitspaket 10. Vorlaeufige Sicherheitsanalyse fuer den Standort Gorleben

    Energy Technology Data Exchange (ETDEWEB)

    Larue, Juergen; Baltes, Bruno; Fischer, Heidemarie; Frieling, Gerd; Kock, Ingo; Navarro, Martin; Seher, Holger

    2013-02-15

    Work package 10 of the preliminary safety analysis for the site Gorleben concerns the analysis of release scenarios and the radiological consequences. The report includes the description of the applied methodology, the concept for the mathematical description of scenarios, the variety of scenarios for the radiological consequence analysis with the definition of the reference scenario. The database for the calculation covers geology and hydrology, the final repository concept and the process of the final disposal system. The used models were the one-phase transport model MARINE and the two-phase transport model TOUGH2. The report summarizes the results including an evaluation of the realization of the demonstration concept with respect to solution transport, fluid transport, robustness of the modeling results and analogy discussion to other disposal variants (i.e. borehole disposal and storage of transport or storage casks).

  20. A consequence index approach to identifying radiological sabotage targets

    International Nuclear Information System (INIS)

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

    1988-01-01

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

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

    International Nuclear Information System (INIS)

    Cowley, W.L.

    1996-01-01

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

  2. Consequence analysis

    International Nuclear Information System (INIS)

    Woodard, K.

    1985-01-01

    The objectives of this paper are to: Provide a realistic assessment of consequences; Account for plant and site-specific characteristics; Adjust accident release characteristics to account for results of plant-containment analysis; Produce conditional risk curves for each of five health effects; and Estimate uncertainties

  3. Radiological consequences of the Chernobyl reactor accident

    International Nuclear Information System (INIS)

    Hill, P.; Hille, R.

    2003-01-01

    The reactor accident at unit 4 of the Chernobyl nuclear power plant in Ukraine has deeply affected the living conditions of millions of people. Especially the health consequences have been of public concern up to the present and also been the subject of sometimes absurd claims. The current knowledge on the radiological consequences of the accident is reviewed. Though an increased hazard for some risk groups with high radiation exposure, e.g., liquidators, still cannot be totally excluded for the future, the majority of the population shows no statistically significant indication of radiation-induced illnesses. The contribution of the Research Center Juelich to the assessment of the post-accidental situation and psychological relief of the population is reported. The population groups still requiring special attention include, in particular, children growing up in highly contaminated regions and the liquidators of the years 1986 and 1987 deployed immediately after the accident. (author)

  4. 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.

  5. Radiological consequences of the Chernobyl reactor accident

    International Nuclear Information System (INIS)

    Hill, P.; Hille, R.

    2002-01-01

    Fifty years of peaceful utilization of nuclear power were interrupted by the reactor accident in unit 4 of the Chernobyl nuclear power station in Ukraine in 1986, a disruptive event whose consequences profoundly affected the way of life of millions of people, and which has moved the public to this day. Releases of radioactive materials contaminated large areas of Belarus, the Russian Federation, and Ukraine. Early damage in the form of radiation syndrome was suffered by a group of rescue workers and members of the reactor operating crew, in some cases with fatal consequences, while the population does not, until now, show a statistically significant increase in the rate of late damage due to ionizing radiation expect for thyroid diseases in children. In particular, no increases in the rates of solid tumors, leukaemia, genetic defects, and congenital defects were detected. For some risk groups exposed to high radiation doses (such as liquidators) the hazard may still be greater, but the large majority of the population need not live in fear of serious impacts on health. Nevertheless, the accident shows major negative social and psychological consequences reinforced by the breakdown of the Soviet Union. This may be one reason for the observed higher incidence of other diseases whose association with the effects of radiation as a cause has not so far been proven. The measurement campaign conducted by the federal government in 1991-1993 addressed these very concerns of the public in an effort to provide unbiased information about exposures detected, on the one hand, in order to alleviate the fears of the public and reduce stress and, on the other hand, to contribute to the scientific evaluation of the radiological situation in the regions most highly exposed. The groups of the population requiring special attention in the future include especially children growing up in highly contaminated regions, and the liquidators of 1986 and 1987 employed in the period immediately

  6. Radiological attacks and accidents. Medical consequences

    International Nuclear Information System (INIS)

    Sakuta, Hidenari

    2007-01-01

    Probability of the occurrence of radiological attacks appears to be elevated after the terrorist attacks against the United States on September 11 in 2001. There are a lot of scenarios of radiological attack: simple radiological device, radiological disperse device (RDD or dirty bomb), attacks against nuclear reactor, improvised nuclear device, and nuclear weapons. Of these, RDD attack is the most probable scenario, because it can be easily made and can generate enormous psychological and economic damages. Radiological incidents are occurring to and fro in the world, including several cases of theft to nuclear facilities and unsuccessful terrorist attacks against them. Recently, a former Russian spy has allegedly been killed using polonium-210. In addition, serious radiological accidents have occurred in Chernobyl, Goiania, and Tokai-mura. Planning, preparation, education, and training exercise appear to be essential factors to cope with radiological attacks and accidents effectively without feeling much anxiety. Triage and psychological first aid are prerequisite to manage and provide effective medial care for mass casualties without inducing panic. (author)

  7. Radiological consequences of gas and oil extraction

    International Nuclear Information System (INIS)

    Kutkov, V.

    2002-01-01

    Contamination of the environment by Technologically Enhanced Naturally Occurring Radioactive Material (TENORM) is a well-known side outcome of gas and oil extraction. Naturally Occurring Radioactive Material (NORM) means material containing the radionuclides of nature origin, i.e., K 40, U 238, Th 232 and their decay products. Technologically Enhanced means, that the physical, chemical, radiological properties, and concentrations of natural radionuclides in NORM have been altered such that there exists a potential for:Redistribution and contamination of environmental media (soil, water, and air); Increased environmental mobility in soils and groundwater; Incorporation of elevated levels of radioactivity in products and construction materials; Improper disposal or use of disposal methods that could result in unnecessary and relatively high exposures to individuals and populations via any environmental pathway and medium. NORM and TENORM are the major sources of human exposure in the World. Their contributions to the worldwide human exposure as evaluated by UNSCEAR. The radiological consequences of occupational and public exposures with TENORM are not clearly monitored and examined. The principal reason of such situation is that for a long time neither ecological organizations nor Regulatory Authorities did not consider the handling of material containing natural radionuclides (other than radon and thoron) as object for regulation of radiation safety. For instance, till now Green peace have not demonstrated any opinion about this problem. TENORM released in oil and gas extraction is a major source of environmental contamination of the Caspian Sea and soils, surface and ground waters in Azerbaijan. The origin of TENORM in oil fields of Apsheron peninsula is related to drilling, production, and processing operations. Other sources of contamination are oil well equipment where separation of contaminated water from oil takes place. Contamination of the environment leads

  8. Radiological terrorism: problems of prevention and minimization of consequences

    International Nuclear Information System (INIS)

    Bolshov, Leonid; Arutyunyan, Rafael; Pavlovski, Oleg

    2008-01-01

    This paper gives a review of the key factors defining the extent of potential hazard caused by ionizing radiation sources for the purpose of radiological terrorism and the key areas of activities in the field of counteractions and minimization of possible consequences of such acts. The importance of carrying out system analysis of the practical experience of response to radiation accidents and elimination of their consequences is emphasized. The need to develop scientific approaches, methods and software to realistically analyze possible scenarios and predict the scale of consequences of the acts of terrorism involving radioactive materials is pointed out. The importance of improvement of radioactive materials accounting, control and monitoring systems, especially in non-nuclear areas, as well as improvement of the legal and regulatory framework governing all aspects of radiation source application in the national economy is of particular importance. (author)

  9. Relative importance of the different radionuclides for radiological consequences

    International Nuclear Information System (INIS)

    Manesse, D.

    1984-12-01

    This paper tries, for several source-terms, to estimate the relative importance of the different families of radioactive products in the calculation of radiological consequences; the study takes place in the case of accidental situations of PWR reactors [fr

  10. The Fukushima accident: radiological consequences and first lessons. Proceedings

    International Nuclear Information System (INIS)

    2012-02-01

    This document brings together the available presentations given at the conference organised by the French society of radiation protection about the Fukushima accident, its radiological consequences and the first lessons learnt. Sixteen presentations (slides) are compiled in this document and deal with: 1 - Accident progress and first actions (Thierry Charles, IRSN); 2 - Conditions and health monitoring of the Japanese intervention teams (Bernard Le Guen, EDF); 3 - The Intra Group action after the Fukushima accident (Michel Chevallier, Groupe Intra; Frederic Mariotte, CEA); 4 - Processing of effluents (Georges Pagis, Areva); 5 - Fukushima accident: impact on the terrestrial environment in Japan (Didier Champion, IRSN); 6 - Consequences of the Fukushima accident on the marine environment (Dominique Boust, IRSN); 7 - Territories decontamination perspectives (Pierre Chagvardieff, CEA); 8 - Actions undertaken by Japanese authorities (Florence Gallay, ASN); 9 - Japanese population monitoring and health stakes (Philippe Pirard, InVS); 10 - Citizen oversight actions implemented in Japan (David Boilley, ACRO); 11 - Implementation of ICRP's (International Commission on Radiological Protection) recommendations by Japanese authorities: first analysis (Jacques Lochard, CIPR); 12 - Control of Japan imported food stuff (David Brouque, DGAL); 13 - Questions asked by populations in France and in Germany (Florence-Nathalie Sentuc, GRS; Pascale Monti, IRSN); 14 - Labour law applicable to French workers working abroad (Thierry Lahaye, DGT); 15 - Protection of French workers working in Japan, Areva's experience (Patrick Devin, Areva); 16 - Fukushima accident experience feedback and post-accident nuclear doctrine (Jean-Luc Godet, ASN)

  11. Stochastic Consequence Analysis for Waste Leaks

    International Nuclear Information System (INIS)

    HEY, B.E.

    2000-01-01

    This analysis evaluates the radiological consequences of potential Hanford Tank Farm waste transfer leaks. These include ex-tank leaks into structures, underneath the soil, and exposed to the atmosphere. It also includes potential misroutes, tank overflow

  12. Analysis of the effect of variations in parameter values on the predicted radiological consequences of geologic disposal of high-level waste

    International Nuclear Information System (INIS)

    Hill, M.D.

    1979-06-01

    A preliminary assessment of the radiological consequences of geologic disposal of high-level waste (Hill and Grimwood. NRPB-R69 (1978)) identified several areas where further research is required before this disposal option can be fully evaluated. This report is an analysis of the sensitivity of the results of the preliminary assessment to the assumptions made and the values of the parameters used. The parameters considered include the leach rate of the waste, the ground-water velocity, the length of the flow path from the repository to a source of drinking water and the sorption constants of the principle radionuclides. The results obtained by varying these parameters are used to examine the effects of assumptions such as the time at which leaching of the waste begins. The sensitivity analysis shows the relative importance of the waste canisters, the waste form and the geologic barrier to radionuclide migration in determining potential doses. These results are used to identify research priorities, establish preliminary design criteria and indicate developments needed in the mathematical modelling of the movement of radionuclides from a repository to the biosphere. (author)

  13. 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

  14. Source term and radiological consequences of the Chernobyl accident

    International Nuclear Information System (INIS)

    Mourad, R.

    1987-09-01

    This report presents the results of a study of the source term and radiological consequences of the Chernobyl accident. The results two parts. The first part was performed during the first 2 months following the accident and dealt with the evaluation of the source term and an estimate of individual doses in the European countries outside the Soviet Union. The second part was performed after August 25-29, 1986 when the Soviets presented in a IAEA Conference in Vienna detailed information about the accident, including source term and radiological consequences in the Soviet Union. The second part of the study reconfirms the source term evaluated in the first part and in addition deals with the radiological consequences in the Soviet Union. Source term and individual doses are calculated from measured post-accident data, reported by the Soviet Union and European countries, microcomputer program PEAR (Public Exposure from Accident Releases). 22 refs

  15. NNSA/NV Consequence Management Capabilities for Radiological Emergency Response

    International Nuclear Information System (INIS)

    Bowman, D. R.

    2002-01-01

    The U.S. Department of Energy's National Nuclear Security Administration Nevada Operations Office (NNSA/NV) provides an integrated Consequence Management (CM) response capability for the (NNSA) in the event of a radiological emergency. This encompasses planning, technical operations, and home team support. As the lead organization for CM planning and operations, NNSA/NV coordinates the response of the following assets during the planning and operational phases of a radiological accident or incident: (1) Predictive dispersion modeling through the Atmospheric Release Advisory Capability (ARAC) at Lawrence Livermore National Laboratory (LLNL) and the High Consequence Assessment Group at Sandia National Laboratories (SNL); (2) Regional radiological emergency assistance through the eight Radiological Assistance Program (RAP) regional response centers; (3) Medical advice and assistance through the Radiation Emergency Assistance Center/Training Site (REAC/TS) in Oak Ridge, Tennessee; (4) Aerial radiological mapping using the fixed-wing and rotor-wing aircraft of the Aerial Measuring System (AMS); (5) Consequence Management Planning Teams (CMPT) and Consequence Management Response Teams (CMRT) to provide CM field operations and command and control. Descriptions of the technical capabilities employed during planning and operations are given below for each of the elements comprising the integrated CM capability

  16. Radiological consequences of radioactive substances in building materials

    International Nuclear Information System (INIS)

    Tschurlovits, M.

    1982-01-01

    A review of radiological consequences of radioactive substances in building materials is given. Where the other contributing papers are dealing with technical problems and measuring techniques, this paper is going beyond the term dose and is considering the risk by radioactive substances in building materials in relation to conventional risks. The present state of international standards is also discussed. If a limit of 1 mSv is adopted, it is shown that this limit is just met at present conditions. (Author) [de

  17. 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

  18. WWER-1000/320 steam generator collector rupture. Radiological consequences

    Energy Technology Data Exchange (ETDEWEB)

    Ivanova, A; Sartmadzhiev, A; Balabanov, E [Energoproekt, Sofia (Bulgaria)

    1996-12-31

    A model describing a hypothetical accident with direct release of primary coolant to the atmosphere is proposed. Cover lifting of the primary collector due to a rupture of the fixing bolts leads to a coolant release. The initial and boundary conditions of the accident scenario have been selected to provide for the most unfavorable conditions. The total release of primary coolant during the first 15 min of transient are estimated to 50.8 tons, of these 48.5 t with the initial activity in the primary coolant circuit. Without evacuation or sheltering, after 7 days of exposure, the expected dose at the boundary of the restricted zone is 0.0182 Sv for the whole body and 0.184 Sv for the thyroid gland. The effective equivalent dose on the site would be 0.0521 Sv. As a result of the analysis it is concluded that the steam generator collector rupture is not jeopardizing the core heat removal even with a minimum configuration of ECCS as the cooling is accomplished through the steam generators. The radiological consequences of the accident would be relatively small if an emergency procedure is applied at the 15-th minute of the transient. 1 ref.

  19. 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

  20. 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.

  1. Consequences of radiological emergencies at Goiania and Mayapuri

    International Nuclear Information System (INIS)

    Sharma, Ranjit; Pradeepkumar, K.S.; Singh, Rajvir

    2012-01-01

    , Morocco and Mayapuri etc. demonstrates the requirement of strict regulatory measures for prevention of loss of control on radioactive sources. Based on the lessons learnt, prevention of such radiological emergencies as well as effective response to reduce the consequences requires strengthening of emergency preparedness at national level. Towards this, installation of radiation detectors at major ports and police patrolling vehicles, training of First Responders and medical community for handling radiological emergency etc are proposed

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

    International Nuclear Information System (INIS)

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

    1989-01-01

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

  3. Evaluation of radiological dispersion/consequence codes supporting DOE nuclear facility SARs

    International Nuclear Information System (INIS)

    O'Kula, K.R.; Paik, I.K.; Chung, D.Y.

    1996-01-01

    Since the early 1990s, the authorization basis documentation of many U.S. Department of Energy (DOE) nuclear facilities has been upgraded to comply with DOE orders and standards. In this process, many safety analyses have been revised. Unfortunately, there has been nonuniform application of software, and the most appropriate computer and engineering methodologies often are not applied. A DOE Accident Phenomenology and Consequence (APAC) Methodology Evaluation Program was originated at the request of DOE Defense Programs to evaluate the safety analysis methodologies used in nuclear facility authorization basis documentation and to define future cost-effective support and development initiatives. Six areas, including source term development (fire, spills, and explosion analysis), in-facility transport, and dispersion/ consequence analysis (chemical and radiological) are contained in the APAC program. The evaluation process, codes considered, key results, and recommendations for future model and software development of the Radiological Dispersion/Consequence Working Group are summarized in this paper

  4. Nuclear energy in Europe and its radiological consequences

    International Nuclear Information System (INIS)

    Kellerer, A.M.

    1993-01-01

    In a popular way, the author deals with the impacts of the Chernobyl reactor accident, and with the scientific relevance of reactions to and discussions about the consequences of peaceful nuclear energy use in Germany. He arrives at the conclusion that the use of nuclear energy in Europe does not have any radiological consequences for its population. Radioactive fission product release during normal operation is completely irrelevant in his view; a controversial problem being the potential release in the case of major accidents. According to the author, however, it would be irrational to put an end to the use of nuclear energy in an area where it shows a high degree of safety, and leave it on its own where it is threatening already now. (orig./HP) [de

  5. Radiological consequence evaluation of DBAs with alternative source term method for a Chinese PWR

    International Nuclear Information System (INIS)

    Li, J.X.; Cao, X.W.; Tong, L.L.; Huang, G.F.

    2012-01-01

    Highlights: ► Radiological consequence evaluation of DBAs with alternative source term method for a Chinese 900 MWe PWR has been investigated. ► Six typical DBA sequences are analyzed. ► The doses of control room, EAB and outer boundary of LPZ are acceptable. ► The differences between AST method and TID-14844 method are investigated. - Abstract: Since a large amount of fission products may releases into the environment, during the accident progression in nuclear power plants (NPPs), which is a potential hazard to public risk, the radiological consequence should be evaluated for alleviating the hazard. In most Chinese NPPs the method of TID-14844, in which the whole body and thyroid dose criteria is employed as dose criteria, is currently adopted to evaluate the radiological consequences for design-basis accidents (DBAs), but, due to the total effective dose equivalent is employed as dose criteria in alternative radiological source terms (AST) method, it is necessary to evaluate the radiological consequences for DBAs with AST method and to discuss the difference between two methods. By using an integral safety analysis code, an analytical model of the 900 MWe pressurized water reactor (PWR) is built and the radiological consequences in DBAs at control room (CR), exclusion area boundary (EAB), low population zone (LPZ) are analyzed, which includes LOCA and non-LOCA DBAs, such as fuel handling accident (FHA), rod ejection accident (REA), main steam line break (MSLB), steam generator tube rupture (SGTR), locked rotor accident (LRA) by using the guidance of the RG 1.183. The results show that the doses in CR, EAB and LPZ are acceptable compared with dose criteria in RG 1.183 and the differences between AST method and TID-14844 method are also discussed.

  6. Consequences of Fukushima 11032011 - Radiological consequences from the nuclear accidents in Fukushima on 11 March 2011

    International Nuclear Information System (INIS)

    2011-12-01

    On 11 March 2011 at 14.46 the strongest earthquake ever recorded in Japan struck the Pacific coast in front of Fukushima. The earthquake and the following tsunami damaged the nuclear power plants in Fukushima Dai-ichi to such an extent that the Japanese government declared the state of catastrophic accident with degree 7 according to the International Nuclear and Radiological Event Scale (INES). At Fukushima Dai-ichi there were 6 boiling water reactors (BWR), a storage pool for spent fuel assemblies and a dry cask storage. 12 km apart at Fukushima Dai-ni there were 4 more BWR. At the moment of the earthquake the reactors 1 to 3 of Fukushima Dai-ichi, as well as the 4 reactors at Fukushima Dai-ni, were at full power, while the reactors 4 to 6 of Fukushima Dai-ichi were shut down for revision. From 12 March 2011 on, fairly large quantities of radioactive materials were released from Fukushima Dai-ichi reactors with meaningful consequences on the population in the near neighbourhood. The irradiation from the radioactivity bearing clouds, the ingestion and inhalation, and the deposit of radioactive materials on the ground threatened the population. The inhabitants of large areas had to be evacuated. Furthermore, radioactive materials contaminated the drinking water, the sea water and finally the plants and animals, i.e. the food chain of the people living there. The Swiss Federal Nuclear Safety Inspectorate (ENSI) continuously proceeded with the evaluation of the situation in Japan and a specialists' team made a detailed analysis of the accident, with emphasis on the human and organisational factors and on the lessons learned from this. The present report describes the present knowledge about the radiological consequences of the accident in Fukushima Dai-ichi on the population in the neighbourhood and on the staff at the power plant, until October 2011. First, the unrolling of the accident and its consequences on the plant site are analysed according to international

  7. 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

  8. Proceeding of the workshop on the results of the cooperative research between JAERI and CHESCIR concerning the study on assessment and analysis of environmental radiological consequences and verification of an assessment system

    Energy Technology Data Exchange (ETDEWEB)

    Amano, Hikaru; Saito, Kimiaki (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-03-01

    This workshop was organized and sponsored by the Japan Atomic Energy Research Institute (JAERI) and Chernobyl Science and Technology Center for International Research (CHESCIR). JAERI and CHESCIR have conducted 8 years research cooperation from 1992 to 1999 concerning the study on assessment and analysis of environmental radiological consequences and verification of an assessment system, focusing on the Chernobyl contaminated area. It contained 3 research subjects. Subject-1 initiated at 1992 and focused the study on measurements and evaluation of environmental external exposure after nuclear accident. Subject-2 initiated at 1992 and focused the study on the validation of assessment models in an environmental consequence assessment methodology for nuclear accidents. Subject-3 initiated at 1995 and focused on the study on migration of radionuclides released into terrestrial and aquatic environment after nuclear accidents. This workshop was held to summarize the research cooperation between JAERI and CHESCIR, and to discuss future research needs in this field. (author)

  9. Estimation of radiological consequences from accidental iodine releases at nuclear power plants

    International Nuclear Information System (INIS)

    Drozdovitch, V.V.

    2001-01-01

    The radiological consequences of a beyond design-basis accident at an NPP for a VVER-1000 reactor are evaluated. Using the software code COSYMA and accounting for radioiodine activity release to the atmosphere at the early stage of the accident, the radionuclide concentration in air and ground deposition densities were estimated. Inhalation and ingestion thyroid doses to different population sub-groups have been calculated. Using modern knowledge about the risk of radiation-induced cancer, the radiological danger of radionuclides released is evaluated for different exposure pathways. Thyroid doses and risk was estimated for populations living at different distances from the NPP. The comparative analysis of exposure pathways and radiological danger of the radionuclides in release during early and intermediate stage of accident has conducted. (author)

  10. OFFSITE RADIOLOGICAL CONSEQUENCE CALCULATION FOR THE BOUNDING MIXING OF INCOMPATIBLE MATERIALS ACCIDENT

    International Nuclear Information System (INIS)

    SANDGREN, K.R.

    2006-01-01

    This document quantifies the offsite radiological consequence of the bounding mixing of incompatible materials accident for comparison with the 25 rem Evaluation Guideline established in Appendix A of DOE-STD-3009. The bounding accident is an inadvertent addition of acid to a waste tank. The calculated offsite dose does not challenge the Evaluation Guideline. Revision 4 updates the analysis to consider bulk chemical additions to single shell tanks (SSTs)

  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. Radiological Consequence Analyses Following a Hypothetical Severe Accident in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Juyub; Kim, Juyoul [FNC Technology Co., Yongin (Korea, Republic of)

    2016-10-15

    In order to reflect the lessons learned from the Fukushima Daiichi nuclear power plant accident, a simulator which is named NANAS (Northeast Asia Nuclear Accident Simulator) for overseas nuclear accident has been developed. It is composed of three modules: source-term estimation, atmospheric dispersion prediction and dose assessment. For the source-term estimation module, the representative reactor types were selected as CPR1000, BWR5 and BWR6 for China, Japan and Taiwan, respectively. Considering the design characteristics of each reactor type, the source-term estimation module simulates the transient of design basis accident and severe accident. The atmospheric dispersion prediction module analyzes the transport and dispersion of radioactive materials and prints out the air and ground concentration. Using the concentration result, the dose assessment module calculates effective dose and thyroid dose in the Korean Peninsula region. In this study, a hypothetical severe accident in Japan was simulated to demonstrate the function of NANAS. As a result, the radiological consequence to Korea was estimated from the accident. PC-based nuclear accident simulator, NANAS, has been developed. NANAS contains three modules: source-term estimation, atmospheric dispersion prediction and dose assessment. The source-term estimation module simulates a nuclear accident for the representative reactor types in China, Japan and Taiwan. Since the maximum calculation speed is 16 times than real time, it is possible to estimate the source-term release swiftly in case of the emergency. The atmospheric dispersion prediction module analyzes the transport and dispersion of radioactive materials in wide range including the Northeast Asia. Final results of the dose assessment module are a map projection and time chart of effective dose and thyroid dose. A hypothetical accident in Japan was simulated by NANAS. The radioactive materials were released during the first 24 hours and the source

  13. 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

  14. Radiologic analysis of amebiasis

    International Nuclear Information System (INIS)

    Kim, S. Y.; Lee, Y. H.; Park, C. Y.

    1980-01-01

    The amebiasis is a common diseases in Korea as well as worldwide especially frequent in tropical area such as India, Africa and South America. The diagnosis of amebiasis remain difficult and complex, despite of many diagnostic method, for example, direct stool test for ameba, many immunologic studies and biopsy. Authors analyzed radiologically the patient who have had confirmed as a amebiasis from June, 1976 to September, 1979 at Yonsei University, College of Medicine, Severance Hospital. The results as follows: 1. The amebic liver abscess was a most common from of the amebiasis in Korea, which were 40 cases among 56 cases. Plain abdomen showed huge hepatomegaly, compression and displacement in hepatic flexure of colon, and reflex gas distension in almost cases. Chest P-A showed nonspecific right lower lung findings from secondary to right upper abdominal pathology, such as elevated right diaphragm (61.3%), pleural effusion (60.0%), right lower lung consolidation (37.5%) and abscess cavities (5.0%). Liver scan showed large space occupying lesion, most commonly situated in right lobe of liver (68.6%). 2. Among total 15 cases of the amebic colitis, positive findings on barium enema were 80%. Barium enama showed spas and irritability (89.2%), narrowing of lumen and lack of distensibility (71.4%) and deformity of cecum (20.0%). Involved site was cecum, ascending colon, rectosigmoid, transeverse and descending colon in order of frequency. Unusual involvement of terminal ileum was 2 cases. 3. Combined cases of amebic liver abscess and colitis were 4 cases (27.7%).

  15. Radiological consequence of Chernobyl nuclear power accident in Japan

    International Nuclear Information System (INIS)

    Uchiyama, Masafumi; Nakamura, Yuji; Kankura, Takako; Iwasaki, Tamiko; Fujimoto, Kenzo; Kobayashi, Sadayoshi.

    1988-03-01

    Two years have elapsed since the accident in Chernobyl nuclear power station shocked those concerned with nuclear power generation. The effect that this accident exerted on human environment has still continued directly and indirectly, and the reports on the effect have been made in various countries and by international organizations. In Japan, about the exposure dose of Japanese people due to this accident, the Nuclear Safety Commission and Japan Atomic Energy Research Institute issued the reports. In this report, the available data concerning the envrionmental radioactivity level in Japan due to the Chernobyl accident are collected, and the evaluation of exposure dose which seems most appropriate from the present day scientific viewpoint was attempted by the detailed analysis in the National Institute of Radiological Sciences. The enormous number of the data observed in various parts of Japan were different in sampling, locality, time and measuring method, so difficulty arose frequently. The maximum concentration of I-131 in floating dust was 2.5 Bq/m 3 observed in Fukui, and the same kinds of radioactive nuclides as those in Europe were detected. (Kako, I.)

  16. Medical social consequences of the safety problems of oncological radiology

    International Nuclear Information System (INIS)

    Pilipenko, M.Yi.; Stadnik, L.L.; Shal'opa, O.Yu.; Rigan, M.M.; Skalets'kij, Yu.M.

    2015-01-01

    Actuality of the problem of patient safety in oncoradiology in Ukraine is grounded. The results of international audit TLD (IAEA/WHO) quality during dosimetry procedures cobalt-telegamma vehicles in Ukraine are investigated, as well as legal and regulatory framework providing for the safety of radiotherapy care, scientific publications on patient safety. Methods: statistical, analytical, bibliographical, systematic approach. On the example of radiation therapy using the results of the international program of the IAEA/WHO TLD audit quality dosimetry calibration devices for remote gamma therapy in Ukraine from 1998 to 2014 the attempt to assess the extent of medical and social consequences of underestimating of medical errors in oncoradiology is made. The problems of regulatory nature of medical errors in oncoradiology are preliminary identified. The problem of medical errors in the treatment of cancer radiation methods in Ukraine is extremely important. Usually the problems of errors in oncoradiology are considered in organizational, technical, personnel and technical aspects, while medical and social consequences of problem are not covered. About 10 thousand of cancer patients in year may suffer from errors related only to dose calculation according to the optimistic variant, while the number of patients for the same period on the pessimistic case can reach 15 thousand. There are a number of legal character problems in oncoradiology related to patient safety that require clarification. The first priority for improving the safety of patients in oncoradiology is the recording and analysis of radiation therapy defects and their consequences

  17. Comparison of potential radiological consequences from a spent-fuel repository and natural uranium deposits

    International Nuclear Information System (INIS)

    Wick, O.J.; Cloninger, M.O.

    1980-09-01

    A general criterion has been suggested for deep geological repositories containing spent fuel - the repositories should impose no greater radiological risk than due to naturally occurring uranium deposits. The following analysis investigates the rationale of that suggestion and determines whether current expectations of spent-fuel repository performance are consistent with such a criterion. In this study, reference spent-fuel repositories were compared to natural uranium-ore deposits. Comparisons were based on intrinsic characteristics, such as radionuclide inventory, depth, proximity to aquifers, and regional distribution, and actual and potential radiological consequences that are now occurring from some ore deposits and that may eventually occur from repositories and other ore deposits. The comparison results show that the repositories are quite comparable to the natural ore deposits and, in some cases, present less radiological hazard than their natural counterparts. On the basis of the first comparison, placing spent fuel in a deep geologic repository apparently reduces the hazard from natural radioactive materials occurring in the earth's crust by locating the waste in impermeable strata without access to oxidizing conditions. On the basis of the second comparison, a repository constructed within reasonable constraints presents no greater hazard than a large ore deposit. It is recommended that if the naturally radioactive environment is to be used as a basis for a criterion regarding repositories, then this criterion should be carefully constructed. The criterion should be based on the radiological quality of the waters in the immediate region of a specific repository, and it should be in terms of an acceptable potential increase in the radiological content of those waters due to the existence of the repository

  18. 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)

  19. Model to predict radiological consequences of transportation accidents involving dispersal of radioactive material in urban areas

    International Nuclear Information System (INIS)

    Taylor, J.M.; Daniel, S.L.

    1978-01-01

    The analysis of accidental releases of radioactive material which may result from transportation accidents in high-density urban areas is influenced by several urban characteristics which make computer simulation the calculational method of choice. These urban features fall into four categories. Each of these categories contains time- and location-dependent parameters which must be coupled to the actual time and location of the release in the calculation of the anticipated radiological consequences. Due to the large number of dependent parameters a computer model, METRAN, has been developed to quantify these radiological consequences. Rather than attempt to describe an urban area as a single entity, a specific urban area is subdivided into a set of cells of fixed size to permit more detailed characterization. Initially, the study area is subdivided into a set of 2-dimensional cells. A uniform set of time-dependent physical characteristics which describe the land use, population distribution, traffic density, etc., within that cell are then computed from various data sources. The METRAN code incorporates several details of urban areas. A principal limitation of the analysis is the limited availability of accurate information to use as input data. Although the code was originally developed to analyze dispersal of radioactive material, it is currently being evaluated for use in analyzing the effects of dispersal of other hazardous materials in both urban and rural areas

  20. A comparison of the radiological consequences of a HEU and LEU fueled research reactor

    International Nuclear Information System (INIS)

    Kollas, J.G.

    1985-01-01

    An analysis of the design basis accident radiological consequences of the HEU and LEU fueled Greek Research Reactor is presented. Doses and individual cancer risk from exposure to the passing radioactive cloud are estimated up to a distance of 20 km from the reactor site. Collective exposure and latent health effects are estimated for the total Athens area of 3081000 inhabitants. The results indicate that the plutonium isotopes buildup in the LEU fuel does not increase appreciably the consequences in respect to the HEU fueled reactor. The plutonium impact concerns mainly bone effects and secondly lung and whole body effects. The contribution to the limiting thyroid dose and the corresponding thyroid effects is insignificant. (author)

  1. Radiological consequences of a human intrusion in a nuclear waste repository in a salt formation

    International Nuclear Information System (INIS)

    Jacquier, P.; Raimbault, P.

    1989-07-01

    The assessment of the consequences of human intrusion scenarios for a repository is very important for salt formations, since this material has an undeniable economic interest. In this work, the scenario considers the solution mining of salt for human consumption: salt is extracted from a cavern; by leaching, this cavern enlarges and uncovers the waste, which falls down into the sump. It was assumed that the intrusion takes place either 500 years or 2500 years after the closing of the repository. High-level vitrified waste or alpha cemented waste were considered. This paper displays the assumptions made and, using a simplified modelling of the phenomena, the estimation of the radiological consequences due to ingestion of contamined sals. A sensitivity/uncertainty analysis is presented which emphasizes several fields where experimental studies have to be pursued or launched [fr

  2. Radiological and toxicological consequences of a worst-case spray leak related to project W-320

    International Nuclear Information System (INIS)

    Himes, D.A.

    1997-01-01

    An analysis was performed of radiological and toxicological consequences of a worst-case leak from a 2-inch diameter flush connection in a pit over tank AY-102. The unmitigated (without controls) flush line spray leak assumes that the blank connector and the removable plug in the pit cover block have been removed so that the maximum system flow is directed out of the open 2-inch line vertically into the air above the pit. The mitigated (with controls) spray scenario assumes the removable plug is in place and the flow is directed against the underside of the pit cover block. The unmitigated scenario exceeded both onsite and offsite risk guidelines for an anticipated accident. For the mitigated case all consequences are well within guidelines and so no additional controls are needed beyond the existing control of having all pit covers and removable plugs in place during any waste transfer

  3. Radiological consequences associated with a human intrusion into a saliferous formation containing a radioactive waste repository

    International Nuclear Information System (INIS)

    Jacquier, P.; Raimbault, P.

    1990-01-01

    Assessment of the consequences of human intrusion scenarios for a repository in salt formations is very important, since this material has an undeniable economic value: it is also a propitious medium for the storage of hydrocarbons, gases, etc. In this work the scenario considers solution mining of salt for human consumption: salt is extracted from a cavern by leaching, and this enlarges the cavern and uncovers the waste, which then falls down into the sump. It was assumed that the intrusion would take place at 500 or even 2500 years after closing of the repository. High activity vitrified waste or cement enrobed alpha waste was considered. This paper sets out the assumptions made and, using simplified modelling of the phenomena, makes an estimation of the radiological consequences associated with ingestion of contaminated salt. A sensitivity/uncertainty analysis which is presented emphasises several fields in which experimental studies should be launched or pursued. (author)

  4. Concepts of optimisation and justification consequences for radiological mass screening

    International Nuclear Information System (INIS)

    Carmichael, J.H.E.

    1987-01-01

    Mass radiological screening campaigns have been mounted in many countries for different conditions and the needs of one country are not necessarily those of another. However, in the European community there is a reasonable uniformity about disease patterns and therefore, a mass screening situation applicable to one country is probably equally applicable throughout the Community. In radiation protection terms, all these potential surveys must be looked at under the same factors. In radiation protection, one thinks first of all justification of the practice. Then one follows it by optimisation of the technique used, so as to obtain the best balance between benefit and detriment, and at this point one must remember that the radiation protection concept of optimisation includes a financial element as well as a purely clinical element and this must lead us on eventually to touch on cost effectiveness. The last portion of the ICRP system is the actual setting of dose limits. Now these are really only applicable to workers not to patients. One cannot set an upper limit on the dose one is prepared to use in a diagnostic radiological examination, but one can say that the dose per examination, should be examined and that the dose range of that examination between various institutions should be ascertained. This should enable any one institution to see where their dose range lies in the larger dose range, and to see that their radiological practice is giving as low a dose as is reasonably achievable

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

    International Nuclear Information System (INIS)

    Vieru, G.

    2001-01-01

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

  6. The influence of the operating schedule of the Greek Research Reactor on the radiological consequences of the reactor

    International Nuclear Information System (INIS)

    Kollas, J.G.

    1986-04-01

    The sensitivity of the radiological consequences of the Greek Research Reactor to the operating schedule of the reactor is assessed in this report. The consequences are due to the occurrence of a postulated accident, a 20% core melt loss of coolant accident. Three different operating schedules are considered: (a) the present 8 hrs/day, 5 days/wk schedule, (b) a 16 hrs/day, 5 days/wk schedule, and (c) a continuous operation schedule. The results of the analysis indicate that there is a direct relation between consequences and duration of operation. (author)

  7. Radiological Dispersal Devices: Select Issues in Consequence Management

    Science.gov (United States)

    2004-03-10

    goals, following which medical treatment of the radiation effects can be provided.10 Post- exposure medical therapy is designed to treat the consequences ...the approach that radiation related health effects can be extrapolated, i.e. the damage caused by radiation exposure CRS-3 8 For example, see Health...effort to determine the validity of these models, the federal government funds research into the health effects of radiation exposure through the

  8. Atmospheric dispersion and the radiological consequences of normal airborne effluents from a nuclear power plant

    International Nuclear Information System (INIS)

    Fang, D.; Yang, L.; Sun, C.Z.

    1995-01-01

    The relationship between the consequences of the normal exhaust of radioactive materials in air from nuclear power plants and atmospheric dispersion is studied. Because the source terms of the exhaust from a nuclear power plant are relatively low and their radiological consequences are far less than the corresponding authoritative limits, the atmospheric dispersion models, their various modifications, and selections of relevant parameters have few effects on those consequences. In the environmental assessment and siting, the emphasis should not be placed on the consequence evaluation of routine exhaust of nuclear power plants, and the calculation of consequences of the exhaust and atmospheric field measurements should be appropriately, simplified. 12 refs., 5 figs., 7 tabs

  9. 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)

  10. Radiological consequences associated with human intrusion into radioactive waste repositories in salt formations

    International Nuclear Information System (INIS)

    Jacquier, P.

    1989-01-01

    The assessment of the radiological impact of human intrusion scenarios is extremely important in the case of repositories located in salt formations, since salt is obviously a valuable economic resource. Salt formations also represent a suitable medium for mining storage caverns for oil and gas. The scenario considered in this report is that of solution mining in salt formations to produce salt for human consumption. It is postulated that the salt is extracted by excavating a cavern through solution-mining and that, in the course of cavern enlargement, the waste is intercepted and drops to the bottom of the cavern. We have assumed that the intrusion takes place 500 or even 2 500 years after the repository has been sealed. The cases considered involve high-level vitrified waste or cemented alpha waste. The paper describes the assumptions on which the scenario is based and uses a simplified model to assess the radiological consequences associated with the ingestion of contaminated salt. The paper also provides details of a sensitivity/uncertainty analysis which identified several areas in which experimental studies should be either initiated or continued [fr

  11. Environmental radiological consequences of a loss of coolant accident

    International Nuclear Information System (INIS)

    Guimaraes, A.C.F.

    1981-01-01

    The elaboration of a calculation model to determine safety areas, named Exclusion Zone and Low Population Zone for nuclear power plants, is dealt with. These areas are determined from a radioactive doses calculation for the population living around the NPP after occurence of a postulated ' Maximum Credible Accident' (MCA). The MCA is defined as an accident with complete loss of primary coolant and consequent fusion of a substantial portion of the reactor core. In the calculations carried out, data from NPP Angra I were used and the assumptions made were conservative, to be compatible with licensing requirements. Under the most pessimistic assumption (no filters) the values of 410m and 1000m were obtained for the Exclusion Zone and Low Population Zone radii, respectivily. (Author) [pt

  12. Analysis of radiology business models.

    Science.gov (United States)

    Enzmann, Dieter R; Schomer, Donald F

    2013-03-01

    As health care moves to value orientation, radiology's traditional business model faces challenges to adapt. The authors describe a strategic value framework that radiology practices can use to best position themselves in their environments. This simplified construct encourages practices to define their dominant value propositions. There are 3 main value propositions that form a conceptual triangle, whose vertices represent the low-cost provider, the product leader, and the customer intimacy models. Each vertex has been a valid market position, but each demands specific capabilities and trade-offs. The underlying concepts help practices select value propositions they can successfully deliver in their competitive environments. Copyright © 2013 American College of Radiology. Published by Elsevier Inc. All rights reserved.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-07-01

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

  14. Radiological consequences of accidents during disposal of spent nuclear fuel in a deep borehole

    International Nuclear Information System (INIS)

    Grundfelt, Bertil

    2013-07-01

    In this report, an analysis of the radiological consequences of potential accidents during disposal of spent nuclear fuel in deep boreholes is presented. The results presented should be seen as coarse estimates of possible radiological consequences of a canister being stuck in a borehole during disposal rather than being the results of a full safety analysis. In the concept for deep borehole disposal of spent nuclear fuel developed by Sandia National Laboratories, the fuel is assumed to be encapsulated in mild steel canisters and stacked between 3 and 5 km depth in boreholes that are cased with perforated mild steel casing tubes. The canisters are joined together by couplings to form strings of 40 canisters and lowered into the borehole. When a canister string has been emplaced in the borehole, a bridge plug is installed above the string and a 10 metres long concrete plug is cast on top of the bridge plug creating a floor for the disposal of the next sting. In total 10 canister strings, in all 400 canisters, are assumed to be disposed of at between 3 and 5 kilometres depth in one borehole. An analysis of potential accidents during the disposal operations shows that the potentially worst accident would be that a canister string is stuck above the disposal zone of a borehole and cannot be retrieved. In such a case, the borehole may have to be sealed in the best possible way and abandoned. The consequences of this could be that one or more leaking canisters are stuck in a borehole section with mobile groundwater. In the case of a leaking canister being stuck in a borehole section with mobile groundwater, the potential radiological consequences are likely to be dominated by the release of the so-called Instant Release Fraction (IRF) of the radionuclide inventory, i.e. the fraction of the radionuclides that as a consequence of the in-core conditions are present in the annulus between the fuel pellets and the cladding or on the grain boundaries of the UO 2 matrix. The

  15. Radiological consequences of accidents during disposal of spent nuclear fuel in a deep borehole

    Energy Technology Data Exchange (ETDEWEB)

    Grundfelt, Bertil [Kemakta Konsult AB, Stockholm (Sweden)

    2013-07-15

    In this report, an analysis of the radiological consequences of potential accidents during disposal of spent nuclear fuel in deep boreholes is presented. The results presented should be seen as coarse estimates of possible radiological consequences of a canister being stuck in a borehole during disposal rather than being the results of a full safety analysis. In the concept for deep borehole disposal of spent nuclear fuel developed by Sandia National Laboratories, the fuel is assumed to be encapsulated in mild steel canisters and stacked between 3 and 5 km depth in boreholes that are cased with perforated mild steel casing tubes. The canisters are joined together by couplings to form strings of 40 canisters and lowered into the borehole. When a canister string has been emplaced in the borehole, a bridge plug is installed above the string and a 10 metres long concrete plug is cast on top of the bridge plug creating a floor for the disposal of the next sting. In total 10 canister strings, in all 400 canisters, are assumed to be disposed of at between 3 and 5 kilometres depth in one borehole. An analysis of potential accidents during the disposal operations shows that the potentially worst accident would be that a canister string is stuck above the disposal zone of a borehole and cannot be retrieved. In such a case, the borehole may have to be sealed in the best possible way and abandoned. The consequences of this could be that one or more leaking canisters are stuck in a borehole section with mobile groundwater. In the case of a leaking canister being stuck in a borehole section with mobile groundwater, the potential radiological consequences are likely to be dominated by the release of the so-called Instant Release Fraction (IRF) of the radionuclide inventory, i.e. the fraction of the radionuclides that as a consequence of the in-core conditions are present in the annulus between the fuel pellets and the cladding or on the grain boundaries of the UO{sub 2} matrix

  16. Model to predict the radiological consequences of transportation of radioactive material through an urban environment

    International Nuclear Information System (INIS)

    Taylor, J.M.; Daniel, S.L.; DuCharme, A.R.; Finley, N.N.

    1977-01-01

    A model has been developed which predicts the radiological consequences of the transportation of radioactive material in and around urban environments. This discussion of the model includes discussion of the following general topics: health effects from radiation exposure, urban area characterization, computation of dose resulting from normal transportation, computation of dose resulting from vehicular accidents or sabotage, and preliminary results and conclusions

  17. Consequence analysis for nuclear reactors, Yongbyon

    International Nuclear Information System (INIS)

    Kang, Taewook; Jae, Moosung

    2017-01-01

    Since the Fukushima nuclear power plant accidents in 2011, there have been an increased public anxiety about the safety of nuclear power plants in Korea. The lack of safeguards and facility aging issues at the Yongbyon nuclear facilities have increased doubts. In this study, the consequence analysis for the 5-MWe graphite-moderated reactor in North Korea was performed. Various accident scenarios including accidents at the interim spent fuel pool in the 5-MWe reactor have been developed and evaluated quantitatively. Since data on the design and safety system of nuclear facilities are currently insufficient, the release fractions were set by applying the alternative source terms made for utilization in the analysis of a severe accident by integrating the results of studies of severe accidents occurred before. The calculation results show the early fatality zero deaths and latent cancer fatality about only 13 deaths in Seoul. Thus, actual impacts of a radiological release will be psychological in terms of downwind perceptions and anxiety on the part of potentially exposed populations. Even considering the simultaneous accident occurrence in both 5-MWe graphite-moderated reactor and 100-MWt light water reactor, the consequence analysis using the MACCS2 code shows no significant damage to people in South Korea. (author)

  18. A methodology for radiological accidents analysis in industrial gamma radiography

    International Nuclear Information System (INIS)

    Silva, F.C.A. da.

    1990-01-01

    A critical review of 34 published severe radiological accidents in industrial gamma radiography, that happened in 15 countries, from 1960 to 1988, was performed. The most frequent causes, consequences and dose estimation methods were analysed, aiming to stablish better procedures of radiation safety and accidents analysis. The objective of this work is to elaborate a radiological accidents analysis methodology in industrial gamma radiography. The suggested methodology will enable professionals to determine the true causes of the event and to estimate the dose with a good certainty. The technical analytical tree, recommended by International Atomic Energy Agency to perform radiation protection and nuclear safety programs, was adopted in the elaboration of the suggested methodology. The viability of the use of the Electron Gamma Shower 4 Computer Code System to calculate the absorbed dose in radiological accidents in industrial gamma radiography, mainly at sup(192)Ir radioactive source handling situations was also studied. (author)

  19. Potential release scenario and radiological consequence evaluation of mineral resources at WIPP

    International Nuclear Information System (INIS)

    Little, M.S.

    1982-05-01

    This report has reviewed certain of the natural resources which may be found at the site of the nuclear waste repository being considered for southeastern New Mexico, and discussed the scenarios which have been used to estimate the radiological consequences from the mining of these resources several hundred years after the radioactive waste has been emplaced. It has been concluded that the radiological consequences of the mining of potash or hydrocarbons (mostly natural gas) are probably bounded by the consequences of hydrologic breach scenarios already considered by the US Department of Energy, and by reports of EEG. These studies conclude that the resultant doses would not constitute a significant threat to public health. This report also evaluates the radiological consequences of solution mining of halite at the WIPP site. Although such mining in the Delaware Basin and particularly at the WIPP site, is not likely at the present time, significant economic, social or climatic changes a few hundred years after emplacement may make these resources more attractive. The DOE did not consider such mining at the site credible

  20. Preliminary radiological consequence estimates for a reference LEU core for PARR

    International Nuclear Information System (INIS)

    Ali Khan, L.

    1990-01-01

    Radiological consequence analysis of a reference LEU core for Pakistan Research Reactor (PARR) has been carried out using mathematical models. It was assumed that 20% of the fuel, having an average burn-up of 50% achieved by continuously operating the reactor for 300 days at 10 MW, fails. It was further assumed that 100% of the noble gases and a fraction of iodine are released. Three modes of leakage from reactor building have been considered. These are exhaust through the normal ventilation system, through emergency ventilation system and leakage from the building. The whole body and thyroid doses have been calculated for 2 hours and 30 days at the boundaries of the exclusion zone at 450m and the low population zone at 1000m. For the releases at stack height through normal and emergency ventilation system, doses at both the boundaries remain within emergency dose limits of 300 rem for thyroid and 25 rem for the whole body. However, in the case of direct release from the containment building, the limiting thyroid dose of 300 rem, at 1000m, for 30 days exposure is achieved for a leak rate of 27% per day under Pasquill condition E. The results presented in this report are only preliminary estimates. A more accurate detailed analysis for various burnups will be carried out using standard computer codes

  1. Preliminary radiological consequence estimate for a reference LEU core for PARR

    International Nuclear Information System (INIS)

    Younus, M.; Khan, L.A.; Akhtar, K.M.; Pervez, S.

    1988-07-01

    Radiological consequence analysis of a reference LEU core for Pakistan Research Reactor (PARR) has been carried out using mathematical models. Three modes of leakage from reactor building have been considered. These are exhaust through the normal ventilation system, through emergency ventilation system and leakage from the building. The whole body and thyroid does have been calculated for the duration of 2 hours and 30 days at the boundaries of exclusion zone at 450m and low population zone at 100m. For the releases at stack height through normal and emergency ventilation systems, does at both the boundaries remain within relevant emergency does limits of 300 rem for thyroid and 25 rem for whole body. However, in case of direct release from the containment building, limiting thyroid does of 300 rem, at 1000m, for 30 days exposure is achieved for a leak rate of 27% per day under Pasquill condition E. The results presented in this report are only preliminary estimates. A more accurate detailed analysis, for various burnups, will be carried using standard computer codes. (orig./A.B)

  2. Roentgeno-radiological examination for ruptures of the main bronchi and their consequences

    International Nuclear Information System (INIS)

    Rabkin, I.Kh.; Kudryavtseva, N.F.; Nersesova, L.I.; Kon'kov, Eh.G.

    1981-01-01

    The results of roentgeno-radiological examination of patients with the main bronchial ruptures show the great diagnostic value of this method of examination. There are 6 types of clinical and x-ray syndromes to be distinguished: gaseous, hemorrhagic, compression, aspiration, ventilatory, perfusive. Both direct and indirect radiomorphological and radiofunctional features of the bronchial ruptures are distinguished. Post-traumatic bronchial stenoses, as well as the results of reconstructive interventions in bronchial ruptures and their consequences are discussed [ru

  3. Inquiry into the radiological consequences of power uprates at light-water reactors worldwide

    International Nuclear Information System (INIS)

    Bilic Zabric, Tea; Tomic, Bojan; Lundgren, Klas; Sjoeberg, Mats

    2007-05-01

    In Sweden, most of the nuclear power plants are planning power uprates within the next few years. The Dept. of Occupational and Medical Exposures at the Swedish Radiation Protection Agency, SSI, has initiated a research project to investigate the radiological implications of power uprates on light-water reactors throughout the world. The project was divided into three tasks: 1. A compilation of power uprates of light-water reactors worldwide. The compilation contains a technical description in brief of how the power uprates were carried out. 2. An analysis of the radiological consequences at four selected Nuclear Power Plants, which was the main objective of the inquiry. Affects on the radiological and chemical situation due to the changed situation were discussed. 3. Review of technical and organisational factors to be considered in uprate projects to keep exposures ALARA. The project was carried out, starting with the collecting of information on the implemented and planned uprates on reactors internationally. The information was catalogued in accordance with criteria focusing on radiological impact. A detailed analysis followed of four plants selected for uprates chosen according to established criteria, in line with the project requirements. The selected plants were Olkiluoto 1 and 2, Cofrentes, Asco and Tihange. The plants were selected with design and operation conditions close to the Swedish plants. All information was compiled to identify good and bad practices that are impacting on the occupational exposure. Important factors were discussed concerning BWRs and PWRs which affect radiation levels and occupational exposures in general, and especially at power uprates. Conclusions related to each task are in detail presented in a particular chapter of the report. Taking into account the whole project and its main objective the following conclusions are considered to be emphasized: Optimisation of the work processes to limit the duration of the time spent in

  4. Inquiry into the radiological consequences of power uprates at light-water reactors worldwide

    Energy Technology Data Exchange (ETDEWEB)

    Bilic Zabric, Tea; Tomic, Bojan; Lundgren, Klas; Sjoeberg, Mats

    2007-05-15

    In Sweden, most of the nuclear power plants are planning power uprates within the next few years. The Dept. of Occupational and Medical Exposures at the Swedish Radiation Protection Agency, SSI, has initiated a research project to investigate the radiological implications of power uprates on light-water reactors throughout the world. The project was divided into three tasks: 1. A compilation of power uprates of light-water reactors worldwide. The compilation contains a technical description in brief of how the power uprates were carried out. 2. An analysis of the radiological consequences at four selected Nuclear Power Plants, which was the main objective of the inquiry. Affects on the radiological and chemical situation due to the changed situation were discussed. 3. Review of technical and organisational factors to be considered in uprate projects to keep exposures ALARA. The project was carried out, starting with the collecting of information on the implemented and planned uprates on reactors internationally. The information was catalogued in accordance with criteria focusing on radiological impact. A detailed analysis followed of four plants selected for uprates chosen according to established criteria, in line with the project requirements. The selected plants were Olkiluoto 1 and 2, Cofrentes, Asco and Tihange. The plants were selected with design and operation conditions close to the Swedish plants. All information was compiled to identify good and bad practices that are impacting on the occupational exposure. Important factors were discussed concerning BWRs and PWRs which affect radiation levels and occupational exposures in general, and especially at power uprates. Conclusions related to each task are in detail presented in a particular chapter of the report. Taking into account the whole project and its main objective the following conclusions are considered to be emphasized: Optimisation of the work processes to limit the duration of the time spent in

  5. 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)

  6. The environmental restoration in the management of radiological accidents with off site consequences

    International Nuclear Information System (INIS)

    Vazquez, C.; Montero, M.; Moraleda, M.; Diaz, J.; Claver, F.; Valles, O.; Rodriguez, N.; Gutierrez, J.

    1998-01-01

    Radiological accidents are among the potential cases of environmental contamination that could have consequences on the health of the population. These accidents, associated with an increase in the level of radiological exposure surpassing the natural background, have been investigated in greater depth than other conventional accidents. This investigation has included the evaluation of their probability, magnitude and consequences in order to establish safety norms. Nevertheless, the social perception of this type of risk appears to be disproportionately high. The development of a comprehensible and adequate standardized system for the evaluation of the radiological risk and the applicability of corrective actions to reduce this type of risk at local level, will undoubtedly contribute to increase the public confidence in the advised options for the restoration of environments contaminated with the long lived radionuclides. This system should consider the local specificity of each contaminated place, and take into account the associated unwanted consequences for each option. This paper presents the first results of a system to help the decision makers in the quantitative evaluation of the radiological risk produced by long lived radionuclides Cs 137, Cs 134 and Sr 90 spread over urban, agricultural and semi-natural environments and the applicable options to reduce it. The evaluation of these applicable options is made considering the reduction of dose that can be reached, the monetary costs and the significant associated secondary effects if there are any. All these factors are integrated for a time period depending on the half-life of the contaminants and on their strength and distribution on the scenario when intervention is being planned. (authors)

  7. Analysis of the Radiology Reports from Radiology Clinics

    International Nuclear Information System (INIS)

    Kim, Eun Jin; Kwack, Kyu Sung; Cho, Jae Hyun; Jang, Eun Ho

    2009-01-01

    The purpose of this study was to investigate the form and content of the radiology reports from radiology clinics in Korea. One hundred and sixty six radiology reports from 49 radiology clinics were collected, and these reports were referred to the academic tertiary medical center from March 2008 to February 2009. These included reports for CT (n = 18), MRI (n = 146) and examinations not specified (n = 2). Each report was evaluated for the presence of required contents (demographics, technical information, findings, conclusion, the name, license number and signature of the radiologist and the referring facility). These requirements were based on the guideline of the American College of Radiology and the previous research. The name of the patient, the gender, the body part, the type of examination, the time of examination and the conclusion, the name of the radiologist and the name of facility were well recorded in over 90% of the radiology reports. However, the identification number of the patient, the referring facility, the referring physician, the use of contrast material, the clinical information, the time of dictation, the signature of the radiologist and the license number of the radiologist were poorly recorded (less than 50%). The optimal format of a radiology report should be established for reliable and valid communication with clinicians

  8. Estimation of radiological consequences from accidental iodine releases at nuclear power plants

    International Nuclear Information System (INIS)

    Drozdovich, V.V.

    2000-01-01

    To evaluate the radiological consequences of a beyond design-basis accident at an NPP for a WWER-1000 reactor, a preliminary investigation was conducted. The scenario of the hypothetical accident was a fast loss of coolant as a result of a rupture in the primary circuit pipeline with diameter of 850 mm and minimum radiation consequences when containment integrity is preserved. Using the software code COSYMA and accounting for radioiodine activity release to the atmosphere at the early stage of the accident, the radionuclide concentration in air and ground deposition densities were estimated. Using modem knowledge about the risk of radiation-induced cancer, the radiological danger of radionuclides released is evaluated for different exposure pathways: (a) extemal exposure from radionuclides in air; (b) extemal exposure from radionuclides deposited on the ground surface; (c) internal exposures from inhalation of radionuclides in air; and (d) internal exposure from ingestion of radionuclides with contaminated foodstuffs. Risk was estimated for populations living at different distances from the source. Preliminary results show that the methodology and models can be applied to the evaluation of radiological danger of an accident at an NPP. Experience from the Chernobyl accident has shown that the damage from a radiation accident can be vast. Expenditures on advanced simulations of the different accident scenarios are worth the cost because they allow radiation protection of populations for these low probability cases, but nevertheless possible accidents at an NPP. (authors)

  9. The Fukushima accident: radiological consequences and first lessons. Proceedings; L'accident de Fukushima: consequences radiologiques et premiers enseignements. Recueil des presentations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-02-15

    This document brings together the available presentations given at the conference organised by the French society of radiation protection about the Fukushima accident, its radiological consequences and the first lessons learnt. Sixteen presentations (slides) are compiled in this document and deal with: 1 - Accident progress and first actions (Thierry Charles, IRSN); 2 - Conditions and health monitoring of the Japanese intervention teams (Bernard Le Guen, EDF); 3 - The Intra Group action after the Fukushima accident (Michel Chevallier, Groupe Intra; Frederic Mariotte, CEA); 4 - Processing of effluents (Georges Pagis, Areva); 5 - Fukushima accident: impact on the terrestrial environment in Japan (Didier Champion, IRSN); 6 - Consequences of the Fukushima accident on the marine environment (Dominique Boust, IRSN); 7 - Territories decontamination perspectives (Pierre Chagvardieff, CEA); 8 - Actions undertaken by Japanese authorities (Florence Gallay, ASN); 9 - Japanese population monitoring and health stakes (Philippe Pirard, InVS); 10 - Citizen oversight actions implemented in Japan (David Boilley, ACRO); 11 - Implementation of ICRP's (International Commission on Radiological Protection) recommendations by Japanese authorities: first analysis (Jacques Lochard, CIPR); 12 - Control of Japan imported food stuff (David Brouque, DGAL); 13 - Questions asked by populations in France and in Germany (Florence-Nathalie Sentuc, GRS; Pascale Monti, IRSN); 14 - Labour law applicable to French workers working abroad (Thierry Lahaye, DGT); 15 - Protection of French workers working in Japan, Areva's experience (Patrick Devin, Areva); 16 - Fukushima accident experience feedback and post-accident nuclear doctrine (Jean-Luc Godet, ASN)

  10. Greenhouse effect: analysis, incertitudes, consequences

    International Nuclear Information System (INIS)

    Perrier, A.

    1991-01-01

    A general presentation of climatic changes due to greenhouse effect with their consequences is analysed. After a schematic description of this effect a simplified atmospheric model (box model) is proposed. This model integrates the main feedback effects and quantifies them. The effects of astronomic and atmospheric factors on climatic changes are analyzed and compared with classical paleoclimatic results. This study shows the need of good global modelization to evaluate long term quantification of climatic greenhouse effects according to the main time lag of the several biospheric boxes. An overview of biologic and agronomic consequences is given to promote new research subjects and to orientate protecting and conservative biospheric actions [fr

  11. Attenuation of radiological consequences from CDA's by radiation. Progress report, October 1, 1976--September 31, 1977

    International Nuclear Information System (INIS)

    Chan, S.H.

    1977-01-01

    This technical progress report summarizes the research work accomplished during the first six months of the investigation on the significance of radiation heat transfer in attenuating the radiological consequences from LMFBR core disruptive accidents. Considerable progress has been made in modeling and computing the effects of radiative cooling on a rising HCDA bubble buoyant through a sodium pool. Our results reveal that most of the fuel vapor within the bubble can be effectively condensed out by radiating cooling. The finding has a profound implication as it could lead to a substantial reduction in subsequent aerosal releases

  12. 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

  13. The Radiological Safety Analysis Computer Program (RSAC-5) user's manual

    International Nuclear Information System (INIS)

    Wenzel, D.R.

    1994-02-01

    The Radiological Safety Analysis Computer Program (RSAC-5) calculates the consequences of the release of radionuclides to the atmosphere. Using a personal computer, a user can generate a fission product inventory from either reactor operating history or nuclear criticalities. RSAC-5 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated through the inhalation, immersion, ground surface, and ingestion pathways. RSAC+, a menu-driven companion program to RSAC-5, assists users in creating and running RSAC-5 input files. This user's manual contains the mathematical models and operating instructions for RSAC-5 and RSAC+. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-5 and RSAC+. These programs are designed for users who are familiar with radiological dose assessment methods

  14. Results of the Czech-Austrian calculations of BDBA radiological consequences

    International Nuclear Information System (INIS)

    Carny, P.; Hohenberg, J.-K.

    2003-01-01

    Full text: Common Czech - Austrian comparisons of codes and calculations of BDBA radiological consequences have been performed. Background of these comparisons is described in the paper presented at this symposium. Results of single steps are summarized and discussed in this poster presentation. From the Czech side calculations have been performed with computer codes PC Cosyma, este, RTARC, HAVAR, HERALD, PTM, RODOS/MATCH and long range code MEDIA used by the Czech meteorological institute (CHMI). Code PC Cosyma is taken as main comparable code in this inter-comparisons as it is used by the Czech and the Austrian side. For every accident scenario and for deterministic as well as probabilistic assessment of accident consequences results of both sides have been practically identical. Computer code 'este' is instrument for projection of release and evaluation of real release under real VVER 440 and WER 1000 emergency conditions. The code can be operated with real radiological, meteorological and technological data from the plant. The code calculates projection of avertable doses and simulates movement of radioactive clouds in the vicinity (up to 40-50 km) of the plant. The code participates in these comparisons as it serves as a support instrument for the staff at the emergency centre of the Czech nuclear regulatory body. Code RTARC (Real Time Accident Release Consequences) serves as an instrument for evaluation of radiation situation in the vicinity of the plant (up to 40 km) during the early phase of an accident. The code participates in these comparisons as it was used in the process of the Czech nuclear power plants protective action planning zone determination. Codes HERALD and HAVAR have been used by Skoda and Energoprojekt for analyses of consequences of design bases accidents in Temelin safety report. They were compared with PC Cosyma in one step of these common calculations by the Czech side. The code HAVAR enables to calculate ingestion doses, too, and

  15. The design and application of a radiological consequence model for tropical and subtropical regions

    International Nuclear Information System (INIS)

    Domel, R.U.; Harris, F.F.; Crawford, J.

    1997-01-01

    The post Chernobyl era has seen the development of a plethora of radiological consequence models. At ANSTO, a model is being developed with a user-friendly interface which will assess the radiological consequences, after an incident, in tropical and sub-tropical climates. The model combines specific regional dispersion and deposition data to determine the dose to man via the major pathways of external and internal irradiation. The external irradiation data will need to include lifestyle information such as time spent L indoors/outdoors, the high/low activity times of the different groups of people (especially critical groups) and shielding factors for housing. The internal irradiation data requires food consumption values, effect of food processing and transfer parameters (soil to plant, plant to animal) to be obtained for tropical and sub-tropical regions. The model allows the user to specify the radionuclide of interest, the age of the person receiving l the dose, race, dietary components and lifestyle. The operator may use a number of default categories, but regional information may also be entered and incorporated into the radiological model allowing assessment of dose to critical groups using site specific data. Initially, the model will deal with the South East Asian region but flexibility has been incorporated into the design to allow application in other regions. A geographic information system is used for display of all input and output data allowing quick access to not only the results but also the underlying assumptions. The model also has portability across computer platforms. The model has been developed to provide a tool for directing future research, has application as a planing tool for emergency response operations but its priority lies in understanding the behaviour of radionuclides in the tropical and sub-tropical environments and their effect on humankind

  16. The design and application of a radiological consequence model for tropical and subtropical regions

    International Nuclear Information System (INIS)

    Domel, R.U.; Harris, F.F.; Crawford, J.

    1998-01-01

    The post Chernobyl era has seen the development of a plethora of radiological consequence models. The information used in these models pertains mostly to temperate and cold climate data, with these data mostly being hard-wired into the body of the model. At the Australian Nuclear Science and Technology Organisation (ANSTO), a model is being developed with a user-friendly interface which will assess the radiological consequences, after an incident, in tropical and sub-tropical climates. The model combines specific regional data (South East Asia) with transfer parameters (soil to plant, plant to animal) obtained for tropical and sub-tropical regions. Flexibility has been incorporated into the the design of the model to allow application in other regions. Where the relevant data are not available, default temperate data are used whilst specific research will be initiated to determine the information required. A Geographic Information System (GIS) is used for the display of input and output data allowing quick access to not only the results but also to the underlying assumptions

  17. ICPP radiological and toxicological sabotage analysis

    International Nuclear Information System (INIS)

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

    1995-01-01

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

  18. Referring physicians' experiences of outsourcing radiological examinations – A variety of views on the consequences

    International Nuclear Information System (INIS)

    Olofsson, P.T.; Blomqvist, L.; Fridell, K.; Aspelin, P.

    2016-01-01

    Introduction: There are strengths, weaknesses, opportunities and challenges when outsourcing advanced radiological examinations such as magnetic resonance examinations from university hospitals to external private institutions. Aim: The aim of this study was to explore the experiences of referring physicians when their referrals for radiological examinations are outsourced from a university hospital in Stockholm, Sweden. Method: This qualitative study is a part of a larger study investigating the consequences of outsourcing referrals for radiological examinations from a university hospital to private external units. Ten referring physicians from orthopedic and oncology departments, representing clinics with large volumes of radiological referrals at a university hospital, were interviewed. Results: The results showed that the requirements for radiological services differ between these specialties. The overall opinion was that examinations performed by external radiology departments needed additional re-assessment work which causes higher costs for their clinics. This indicates that there is insufficient communication between referring physicians and the radiological department at the University Hospital. Conclusions: For better planning of radiological services, radiology departments must consider the referring physicians' needs and develop suitable contract when organizing the practice of outsourcing. The management structure in radiology departments and communication between referring physicians and radiologists in the radiology departments should be studied further, to promote better understanding and improve the efficiency of the outsourcing process. - Highlights: • The requirements for radiological services differ between specialties. • Outsourced examinations need more frequent re-assessment. • Outsourced examinations cause higher costs for referring departments. • Outsourcing radiological examinations entail more administrative work.

  19. Radiological release analysis for the EFR project

    International Nuclear Information System (INIS)

    Carluec, B.; Dechelette, S.; Balard, F.

    1996-01-01

    Tile safety approach of the European Fast Reactor project (EFR) requires to deal with certain hypothetical CDA and therefore to enhance the containment structure in order to mitigate the consequences. The analyses are performed in order to design a containment taking advantages of die inherent characteristics of the liquid metal fast reactor. Adequate computer codes describing the sequences which follow the core disruptive accident, are used. One of the main tool is the computer code CONTAIN-LMR. The goal of these analyses is to identify the most sensitive phenomena such as the overpressure due to sodium fire, to assess the involvement of some design parameters such as the leaktightness of the structures, the arrangement of the ventilation system- the effects of the implementation of filters or a retention chamber. The results of the calculations allow to propose a robust containment for EFR, and to verify that the radiological releases in the environment can be limited. The paper presents the safety approach of EFR adopted with regard to the accidents leading to a radiological source term, and the main design options retained for the containment of EFR. Then, the methods used to describe the phenomena and some representative calculations, will be presented. The main useful information and knowledge which derive from these studies for the designers conclude the paper. (author)

  20. Evaluation of the radiological consequences of a human intrusion in a granite formation

    International Nuclear Information System (INIS)

    Mejon-Goula, M.J.; Cernes, A.

    1989-07-01

    The methodology used in France for the evaluation of the radiological consequences associated to a nuclear waste repository in a deep geological formation is the deterministic one. This means that, in addition to the calculations in connection with the ''normal'' scenario, a limited number of ''altered'' scenarios, representing the different families of plausible scenarios and corresponding to the most important consequences resulting from there families, have to be taken into account. Among them, the human intrusion scenario is an important one. In a study performed inside the CEC PAGIS project and also for a french expert group (Goguel group) which carried out a methodologic work for the national site selection procedure, results concerning the quantification of the radiological consequences of a human intrusion have been obtained without attempting at the evaluation of its probability. The intrusion time ranged from 1 000 to 100 000 years and different contamination scenarios were taken into account. It was assumed that the intrusion led to the creation of a 100 cubic meters edge cubic cavity in the immediate vicinity to the repository. Using the description of the Auriat site realized for PAGIS, the calculation was performed in three steps: - calculation of the evolution of the repository until the intrusion time, - computation of the supposed instantaneous new flow distribution after the intrusion, - computation of the dose rate, using the mean volumic activity in the cavity walls and the outgoing flow rate. Three exposure scenarios were considered: - a worker in the mine exposed to by external irradiation and contaminated by inhalation of radioactive materials, -an animal drinking in the vicinity during the mining operation, - gardening after the closure of the mine. With the exception of the worker scenario (the dose rate may reach 10 -2 Sv/year, which is comparable with the normal exposure in a granite mine), the other dose rates were found to be quite low

  1. The Fukushima Daiichi Accident. Technical Volume 4/5. Radiological Consequences

    International Nuclear Information System (INIS)

    2015-08-01

    description of the main aspects of radiation protection related to the accident at the Fukushima Daiichi NPP. Section 4.4 presents a review of post-accident studies of the health of members of the public and workers, including the possible radiation induced health effects and psychological consequences to individuals resulting from the accident. Section 4.5 covers the impact of the radioactive releases from the Fukushima Daiichi NPP on the environment (more specifically on non-human biota). The International Commission on Radiological Protection (ICRP) methodology has been applied to estimate dose and effects to a range of reference animals and plants from the marine, terrestrial and freshwater environments. There are 2 appendices and 12 annexes that provide supplementary information. Appendix I contains maps of levels of radioactivity and radionuclides in the environment. Appendix II provides details of a statistical analysis of individual dose data. The annexes are included on the CD-ROM attached to this volume and provide the following information: – Annex I: Characteristics and measurement of radioactivity and radiation levels. – Annex II: Local and regional meteorological conditions in east Japan during 11–23 March 2011. – Annex III: Levels of radioactivity in the terrestrial environment. – Annex IV: Radioactivity in the marine environment arising from releases following the Fukushima Daiichi accident. – Annex V: UNSCEAR assessment of the dose to the public

  2. An assessment of the radiological consequences of the Greek Research Reactor's design basis accident with the use of low enriched uranium

    International Nuclear Information System (INIS)

    Kollas, J.G.

    1985-09-01

    An analysis of the radiological consequences of the design basis accident in the low enriched uranium fueled 5 MW Greek Research Reactor is presented. For the source term thirty-five isotopes are taken into consideration and conservative figures of fission product release are adopted. To estimate the reactor's consequences for Athens population a CRAC2 consequence model version is used. The results indicate that limiting dose and effects are respectively the thyroid dose and the thyroid effects induced in the 3,081,000 inhabitants of Athens region. (author)

  3. 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.)

  4. 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.)

  5. Radiological and environmental consequences. Final report of the Nordic Nuclear Safety Research project BOK-2

    International Nuclear Information System (INIS)

    Palsson, S.E.

    2002-11-01

    Final report of the Nordic Nuclear Safety Research project BOK-2, Radiological and Environmental Consequences. The project was carried out 1998-2001 with participants from all the Nordic countries. Representatives from the Baltic States were also invited to some of the meetings and seminars. The project consisted of work on terrestrial and marine radioecology and had a broad scope in order to enable participation of research groups with various fields of interest. This report focuses on the project itself and gives a general summary of the studies undertaken. A separate technical report summarises the work done by each research group and gives references to papers published in scientific journals. The topics in BOK-2 included improving assessment of old and recent fallout, use of radionuclides as tracers in Nordic marine areas, improving assessment of internal doses and use of mass spectrometry in radioecology. (au)

  6. Regional potential radiological consequences and their variability of failtRe events in a reprocessing plant

    International Nuclear Information System (INIS)

    Paretzke, H.G.; Friedland, W.; Geiss, H.; Muller, H.; Prohl, G.

    1984-01-01

    A computer program system has been developed for best estimate assessments of radiological consequences of accidental atmospheric releases of radionuclides. Computerized data bases as realistic as possible have been established and used describing weather sequences, land topography and usage, human population density, yield of agricultural products, etc. Input from the complex atmospheric transport program MUSEMEI and from the food chain program ECOSYS is combined with the main program BAMBUS to calculate site specific probability distributions for individual and regional collective exposures as functions of the time of year of the release, spatial location, exposure pathway, etc. In this paper, the principles of the program system are described and examples are given for its application to a selected hypothetical failure event in a reprocessing plant

  7. A model for radiological consequences of nuclear power plant operational atmospheric releases

    International Nuclear Information System (INIS)

    Kocar, Cemil; Soekmen, Cemal Niyazi

    2009-01-01

    A dynamic dose and risk assessment model is developed to estimate radiological consequences of atmospheric 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. The model allows to simulate interregional moves of people and multi-location food supply in the computational domain. Any long-range atmospheric dispersion model which yields radionuclide concentrations in air and on the ground at predetermined time intervals can easily be integrated into the model. The software developed is validated against radionuclide concentrations measured in different environmental media and dose values estimated after the Chernobyl accident. Results obtained using the model compare well with dose estimates and activities measured in foodstuffs and feedstuffs

  8. The radiological consequences of releases from nuclear facilities to the aquatic environment

    International Nuclear Information System (INIS)

    Preston, A.

    1975-01-01

    The release of radioactive materials to the environment is an inescapable consequence of the utilization of nuclear energy. The objective therefore is to decide on what basis and against what criteria regulatory action should be taken to protect the environment against the impact of radioactive substances. In properly regulated situations releases of such material will be minor in character and their radiological implications will rest largely in the field of public health. There are now some three decades of experience in respect of the environmental impact of radioactive materials, and certain major conclusions can be drawn. This paper reviews this experience in broad terms, and draws conclusions relevant to the regulatory problem. Future problems, especially in the context of an expanding use of nuclear power, are considered and priority research needs and opportunities indicated. (author)

  9. Radiological consequences of the reactor accident at Three Mile Island, Pennsylvania, USA

    International Nuclear Information System (INIS)

    Bryant, P.M.

    1979-01-01

    The findings of the Ad Hoc Population Dose Assessment Group are reviewed and summarized (Population Dose and Health Impact of the Accident at the Three Mile Island Nuclear Station. A preliminary assessment for the period March 28 through April 7, 1979; May 10, 1979. Washington DC, US Government Printing Office, 1979). The principal radionuclides released were xenon-133 and xenon-135, with some iodine-131. External exposure to gamma radiation was estimated from TLDs positioned at various on-site and off-site locations. Lung exposure from inhaled xenon-133 was calculated and air and milk monitoring results gave potential dose equivalents to a child's thyroid. These numerical estimates will be further refined, but only minor corrections to the present values are anticipated. The findings of this preliminary assessment have indicated that the radiological consequences to the public of the reactor accident are minimal. (UK)

  10. Conceptual Framework for Physical Protection Against Sabotage Considering Plant-specific Radiological Consequences

    International Nuclear Information System (INIS)

    Lee, Joung Hoon; Yu, Dong Han

    2010-01-01

    According to the Generation IV (Gen IV) Technology Roadmap, Gen IV nuclear energy systems (NESs) should highlight proliferation resistance and physical protection (PR and PP) as one of the four goals along with sustainability, safety and reliability, and economics. Especially, physical protection (PP) is the typical important characteristic of an NES that impedes the theft of materials suitable for nuclear explosives or radiation dispersal devices (RDD) and the sabotage of facilities and transportation by subnation entities and other non-Host State adversaries. These two subjects have been studied separately. Proliferation is commonly considered as an international concern and the past work on the PR assessments can be found. On the other hands, PP is regarded as a State security concern, much of which is classified and facility-dependent. Recently, more concern has been focused on the PP design and regulation because of rapid environment changes including radiological consequences by internal sabotage and nuclear terrorism by RDDs. The current PP Regulation has been applied intensively to the existing nuclear facilities and could be a possible guidance for the future GEN-IV NESs. This paper first reviews the IAEA guide document, INFCIRC/225, which was accepted as the standard international guideline in the physical protection area. It has been updated several times up to now, and is undergoing another revision. The paper introduces current substantial changes in the document regarding PP including the national nuclear security and sabotage in the nuclear facilities. Then, it presents a conceptual framework for physical protection against sabotage considering plant-specific radiological consequence after malicious acts within certain vital areas. The framework combines the newly developed method of vital area identification, the current PSA level 2 works, and physical protection concepts. This would help to improve a design concept of new physical protection

  11. Transport of radioactive material in Romania -the assessment of the radiological consequences and the environmental impacts

    International Nuclear Information System (INIS)

    Vieru, Gheorghe

    2008-01-01

    The transport of radioactive materials (RAM) is a very important problem considering the potential risks and radiological consequences in carrying-out this activity. Romania as a Member State of the International Atomic Energy Agency has implemented national regulations for a safe transport of RAM in accordance with the Agency's recommendations as well as other international specialized organizations. Based on the IAEA's Safety Standard-TS-R-1 (ST-1), Romanian National Nuclear Regulatory Body - CNCAN adopted and implemented, by Act no. 357/December 21, 2005, the safety regulations for the transport of radioactive materials in Romania under the title: 'Regulations for the Transport of Radioactive Materials'. The paper will present the main sources of radioactive materials in Romania their transportation routes with a particular interest paid to the radioactive wastes (low level radioactive materials), isotopes and radioactive sources, uranium ore. Starting from the fact that the safety in the transport of radioactive materials is dependent on appropriate packaging for the contents being shipped, rather than operational and/or administrative actions required for the package, the paper presents, briefly the main packages used for transport and storage of such RAM in Romania. There are presented hypothetical scenarios for specific problems related to the identification and evaluation of the risks and potential radiological consequences associated with the transport of radioactive materials in Romania, for all these three situations: routine transport (without incidents), normal transport (with minor incidents) and during possible accidents. As a conclusion, it is ascertained that the evaluated annual collective dose for the population due to RAM transport is less than that received by natural radiation sources. At the same time it is concluded that Romanian made packages are safe and prevent loss of their radioactive contents into the environment. (author)

  12. Conceptual Framework for Physical Protection Against Sabotage Considering Plant-specific Radiological Consequences

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Joung Hoon; Yu, Dong Han [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

    2010-10-15

    According to the Generation IV (Gen IV) Technology Roadmap, Gen IV nuclear energy systems (NESs) should highlight proliferation resistance and physical protection (PR and PP) as one of the four goals along with sustainability, safety and reliability, and economics. Especially, physical protection (PP) is the typical important characteristic of an NES that impedes the theft of materials suitable for nuclear explosives or radiation dispersal devices (RDD) and the sabotage of facilities and transportation by subnation entities and other non-Host State adversaries. These two subjects have been studied separately. Proliferation is commonly considered as an international concern and the past work on the PR assessments can be found. On the other hands, PP is regarded as a State security concern, much of which is classified and facility-dependent. Recently, more concern has been focused on the PP design and regulation because of rapid environment changes including radiological consequences by internal sabotage and nuclear terrorism by RDDs. The current PP Regulation has been applied intensively to the existing nuclear facilities and could be a possible guidance for the future GEN-IV NESs. This paper first reviews the IAEA guide document, INFCIRC/225, which was accepted as the standard international guideline in the physical protection area. It has been updated several times up to now, and is undergoing another revision. The paper introduces current substantial changes in the document regarding PP including the national nuclear security and sabotage in the nuclear facilities. Then, it presents a conceptual framework for physical protection against sabotage considering plant-specific radiological consequence after malicious acts within certain vital areas. The framework combines the newly developed method of vital area identification, the current PSA level 2 works, and physical protection concepts. This would help to improve a design concept of new physical protection

  13. RadCon: A radiological consequences model. Technical guide - Version 2.0

    International Nuclear Information System (INIS)

    Crawford, J; Domel, R.U.; Harris, F.F.; Twining, J.R.

    2000-05-01

    A Radiological Consequence model (RadCon) is being developed at ANSTO to assess the radiological consequences, after an incident, in any climate, using appropriate meteorological and radiological transfer parameters. The major areas of interest to the developers are tropical and subtropical climates. This is particularly so given that it is anticipated that nuclear energy will become a mainstay for economies in these regions within the foreseeable future. Therefore, data acquisition and use of parameter values have been concentrated primarily on these climate types. Atmospheric dispersion and deposition for Australia can be modelled and supplied by the Regional Specialised Meteorological Centre (RSMC, one of five in the world) which is part of the Bureau of Meteorology Research Centre (BMRC), Puri et al. (1992). RadCon combines these data (i.e. the time dependent air and ground concentration generated by the dispersion model or measured quantities in the case of an actual incident) with specific regional parameter values to determine the dose to people via the major pathways of external and internal irradiation. For the external irradiation calculations, data are needed on lifestyle information such as the time spent indoors/outdoors, the high/low physical activity rates for different groups of people (especially critical groups) and shielding factors for housing types. For the internal irradiation calculations, data are needed on food consumption, effect of food processing, transfer parameters (soil to plant, plant to animal) and interception values appropriate for the region under study. Where the relevant data are not available default temperate data are currently used. The results of a wide ranging literature search has highlighted where specific research will be initiated to determine the information required for tropical and sub-tropical regions. The user is able to initiate sensitivity analyses within RadCon. This allows the parameters to be ranked in

  14. Assumptions used for evaluating the potential radiological consequences of a less of coolant accident for pressurized water reactors - June 1974

    International Nuclear Information System (INIS)

    Anon.

    1974-01-01

    Section 50.34 of 10 CFR Part 50 requires that each applicant for a construction permit or operating license provide an analysis and evaluation of the design and performance of structures, systems, and components of the facility with the objective of assessing the risk to public health and safety resulting from operation of the facility. The design basis loss of coolant accident is one of the postulated accidents used to evaluate the adequacy of these structures, systems, and components with respect to the public health and safety. This guide gives acceptable assumptions that may be used in evaluating the radiological consequences of this accident for a pressurized water reactor. In some cases, unusual site characteristics, plant design features, or other factors may require different assumptions which will be considered on an individual case basis. The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position

  15. Assumptions used for evaluating the potential radiological consequences of a loss of coolant accident for boiling water reactors - June 1974

    International Nuclear Information System (INIS)

    Anon.

    1974-01-01

    Section 50.34 of 10 CFR Part 50 requires that each applicant for a construction permit or operating license provide an analysis and evaluation of the design and performance of structures, systems, and components of the facility with the objective of assessing the risk to public health and safety resulting from operation of the facility. The design basis loss of coolant accident is one of the postulated accidents used to evaluate the adequacy of these structures, systems, and components with respect to the public health and safety. This guide gives acceptable assumptions that may be used in evaluating the radiological consequences of this accident for a pressurized water reactor. In some cases, unusual site characteristics, plant design features, or other factors may require different assumptions which will be considered on an individual case basis. The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position

  16. The Fukushima Daiichi Accident. Technical Volume 4/5. Radiological Consequences. Annexes

    International Nuclear Information System (INIS)

    2015-08-01

    The Fukushima Daiichi Accident consists of a Report by the IAEA Director General and five technical volumes. It is the result of an extensive international collaborative effort involving five working groups with about 180 experts from 42 Member States with and without nuclear power programmes and several international bodies. It provides a description of the accident and its causes, evolution and consequences, based on the evaluation of data and information from a large number of sources available at the time of writing. The Fukushima Daiichi Accident will be of use to national authorities, international organizations, nuclear regulatory bodies, nuclear power plant operating organizations, designers of nuclear facilities and other experts in matters relating to nuclear power, as well as the wider public. The set contains six printed parts and five supplementary CD-ROMs. Contents: Report by the Director General; Technical Volume 1/5, Description and Context of the Accident; Technical Volume 2/5, Safety Assessment; Technical Volume 3/5, Emergency Preparedness and Response; Technical Volume 4/5, Radiological Consequences; Technical Volume 5/5, Post-accident Recovery; Annexes. The Report by the Director General is available separately in Arabic, Chinese, English, French, Russian, Spanish and Japanese

  17. Radiological consequences of possible irradiation scenarios in military practice in Ukraine

    International Nuclear Information System (INIS)

    Vyinnyikov, V.A.; Kulyinyich, G.V.; Chernyavs'kij, Yi.Yu.

    2017-01-01

    For the first time the logical and handy classification of possible radiation exposure scenarios in military practice is presented. It combines the causal situation, the type of battle task and early clinical effects, which lead to the reduction of the work efficiency of the personnel. Five causal situations are distinguished; each containing from one to three variants of the contact with ionizing radiation; and for each particular scenario the specific symptoms of early biomedical effects of the external and/or internal irradiation are presented. The assessment of the work efficacy of military units has to be based of the criteria of the grade and frequency distribution of the general primary reaction on the irradiation. The consequences of radiation exposure are listed in the ascending order of their health danger: from the radiophobia up to the toxaemic or cerebral forms of acute radiation syndrome, early transitive disability syndrome and combined radiation-traumatic or radiation-termal injuries. The clinical consequences of radiation exposure, which determine the loss of work efficiency of military subdivisions, vary essentially depending on the scenario of irradiation. The underestimation of the full possible spectrum of radiological effects beyond the acute radiation syndrome may lead to the mistakes in the evaluation of the personnel losses during the war time. Further optimization of the military radiation safety system requires the establishing of clear quantitative coefficients linking various clinical radiation symptoms and the losses of work efficiency in exposed military units.

  18. Two decades of radiological accidents direct causes, roots causes and consequences

    Directory of Open Access Journals (Sweden)

    Rozental Jose de Julio

    2002-01-01

    Full Text Available Practically all Countries utilize radioisotopes in medicine, industry, agriculture and research. The extent to which ionizing radiation practices are employed varies considerably, depending largely upon social and economic conditions and the level of technical skills available in the country. An overview of the majority of practices and the associated hazards will be found in the Table IV to VII of this document. The practices in normal and abnormal operating conditions should follow the basic principles of radiation protection and the Safety of Radiation Sources, considering the IAEA Radiation Protection and the Safety of Radiation Sources, Safety Series 120 and the IAEA Recommendation of the Basic Safety Standards for Radiation Protection, Safety Series Nº 115. The Standards themselves underline the necessity to be able to predict the radiological consequences of emergency conditions and the investigations that should need to be done. This paper describes the major accidents that had happened in the last two decades, provides a methodology for analyses and gives a collection of lessons learned. This will help the Regulatory Authority to review the reasons of vulnerabilities, and to start a Radiation safety and Security Programme to introduce measurescapable to avoid the recurrence of similar events. Although a number of accidents with fatalities have caught the attention of the public in recent year, a safety record has accompanied the widespread use of radiation sources. However, the fact that accidents are uncommon should not give grounds for complacency. No radiological accident is acceptable. From a radiation safety and security of the sources standpoint, accident investigation is necessary to determine what happened, why, when, where and how it occurred and who was (were involved and responsible. The investigation conclusion is an important process toward alertness and feedback to avoid careless attitudes by improving the comprehension

  19. A Study on Establishment of Unacceptable Radiological Consequence (URC) for Physical Protection against Sabotage

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Myungtak; Koh, Moonsung; Lee, Youngwook; Jo, Kwang Ho [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

    2014-05-15

    The international community has recommended that a graded approach should be applied to the establishment of the domestic regime for physical protection in accordance with fundamental principle H of the amended Convention on Physical Protection of Nuclear Material (CPPNM) and INFCIRC/225/rev.5. In Korea, Currently, the graded approach to unauthorized removal of nuclear material is divided into three categories (Category Ι, Category ΙΙ, Category ΙΙΙ) based on the IAEA INFCIRC/225/rev.5. Moreover, depending on the categorization of nuclear material, physical protection measures against unauthorized removal are also clearly categorized. But in the case of physical protection against sabotage, the graded approach to the physical protection measures is not applied since Unacceptable Radiological Consequence (URC) for identifying sabotage target and level is not determined. URC can be established based on either dose limit or design limit. The report by Sandia National Lab. in USA specifies that core damage is used for URC. Calculation of an exact dose is based on various assumptions and processes and subsequently increases uncertainty. Therefore, using design limit for decreasing uncertainty is more effective than using dose limit. In order to apply the graded approach to physical protection against sabotage, we have taken into Fundamental principle H : Physical protection requirements should be based on a graded approach, taking into account the current evaluation of the threat, the relative attractiveness, the nature of the material and potential consequences associated with the unauthorized removal of nuclear material and with the sabotage against nuclear material of nuclear facilities consideration legal and institutional standards on domestic and international radiological consequences and intended to provide a reference for the URC establishment by the State. The study on various standards led to the conclusion that each value has advantages and

  20. Research and managing institutions in Ukraine concerning the radiological consequences of the Chernobyl accident

    International Nuclear Information System (INIS)

    Nasvit, O.

    1998-01-01

    The paper presents temporal changes of the national organizations in managing the Chernobyl accident and its activities. The National Academy of Sciences of Ukraine started its activity from the first days after the accident. In 1990 a special executive body, the State committee of Chernobyl Affairs was established in Ukraine to manage the whole activity to overcome the Chernobyl problems. In 1991 it was rearranged into the Ministry of Chernobyl Affairs. In 1996 a new Ministry of Ukraine on Emergences and Affairs of Population Protection from the Consequences of Chernobyl Catastrophe(MEA) was founded on the basis of the Min. Chernobyl and Headquarters Staff of Civil Defence. The National Commission on Radiological Protection of Ukraine (NCRPU) belongs to the Parliament structure. NCRPU is responsible for approval of radiological safety standards and derived regulations. Very often the regulation approved are stricter than the international recommendations. There is an essential lack of attention within the Parliament to the activity of NCRPU. Ministry of Health is responsible for all kinds of medical care for the people suffering from the Chernobyl Catastrophe. In order to provide permanent medical service, a nation-wide scheme has been worked out. Scientific Center for Radiation Medicine is the leading scientific institute of the Academy of Medical Sciences. The State scientific Center of Environmental Radio geochemistry was created in 1996 on the basis of the two departments of the Institute of Geochemistry. The Center was created in order to improve coordination and managing of scientific researches on the behavior of artificial and natural radionuclides and chemical substances in the environment etc.. The Chernobyl Scientific-Technical center for International Research was created in March,1996. The Ukrainian Scientific Hygienic Center of Ministry of Health was created in 1989 and included two institutions. The subjects, the direction of research works

  1. Off-site consequences of radiological accidents: methods, costs and schedules for decontamination

    International Nuclear Information System (INIS)

    Tawil, J.J.; Bold, F.C.; Harrer, B.J.; Currie, J.W.

    1985-08-01

    This report documents a data base and a computer program for conducting a decontamination analysis of a large, radiologically contaminated area. The data base, which was compiled largely through interviews with knowledgeable persons both in the public and private sectors, consists of the costs, physical inputs, rates and contaminant removal efficiencies of a large number of decontamination procedures. The computer program utilizes this data base along with information specific to the contaminated site to provide detailed information that includes the least costly method for effectively decontaminating each surface at the site, various types of property losses associated with the contamination, the time at which each subarea within the site should be decontaminated to minimize these property losses, the quantity of various types of labor and equipment necessary to complete the decontamination, dose to radiation workers, the costs for surveying and monitoring activities, and the disposal costs associated with radiological waste generated during cleanup. The program and data base are demonstrated with a decontamination analysis of a hypothetical site. 39 refs., 24 figs., 155 tabs

  2. Off-site consequences of radiological accidents: methods, costs and schedules for decontamination

    Energy Technology Data Exchange (ETDEWEB)

    Tawil, J.J.; Bold, F.C.; Harrer, B.J.; Currie, J.W.

    1985-08-01

    This report documents a data base and a computer program for conducting a decontamination analysis of a large, radiologically contaminated area. The data base, which was compiled largely through interviews with knowledgeable persons both in the public and private sectors, consists of the costs, physical inputs, rates and contaminant removal efficiencies of a large number of decontamination procedures. The computer program utilizes this data base along with information specific to the contaminated site to provide detailed information that includes the least costly method for effectively decontaminating each surface at the site, various types of property losses associated with the contamination, the time at which each subarea within the site should be decontaminated to minimize these property losses, the quantity of various types of labor and equipment necessary to complete the decontamination, dose to radiation workers, the costs for surveying and monitoring activities, and the disposal costs associated with radiological waste generated during cleanup. The program and data base are demonstrated with a decontamination analysis of a hypothetical site. 39 refs., 24 figs., 155 tabs.

  3. Guidelines for calculation of atmospheric dispersion and radiological consequences of design basis reactor accidents - Severe accident calculation guidelines, EPR

    International Nuclear Information System (INIS)

    Martens, R.; Schmitz, B.M.; Horn, M.

    1999-01-01

    The activities carried out within the (reduced) project period (1. Sept. until 31. Dec. 1998) for coordinated harmonization between France and Germany, of guidelines for calculation of the radiological consequences of a severe reactor accident, are summarized. (orig./CB) [de

  4. Legislation in Ukraine about the radiological consequences of the Chernobyl accident

    International Nuclear Information System (INIS)

    Nasvit, O.

    1998-01-01

    The paper describes the status and consequences of the principal laws of Ukraine concerning the problem of the Chernobyl catastrophe. The Ukrainian authorities have been giving a series of the laws after February, 1991. The system of Chernobyl Laws in Ukraine reflects the rather good intention of the Ukrainian authorities to help the people who suffered from the Chernobyl catastrophe. The system of the Laws includes more than that justified by the scientific base, that is, the combined effect of radioactive exposure and factors of non-radioactive synergism. However, after the Soviet Union collapse, it was found that the Laws were overloaded with social payments and compensations. A number of changes and additions to the Laws caused political struggles. In this situation, the radiological aspect of the problems stepped aside. The radiological survey system in Ukraine provides necessary information on annual doses to the population in the contaminated areas. Despite of the clearly observed reduction of the doses, allocation on the categories of contaminated zones has not been reviewed since 1991. According to the monitoring data, the level of radiation doses of about 50 % of all settlements does not correspond to their present status. What is very important in the present situation is to stop compulsory resettlement. It is necessary to stop to pay compensations for contaminated food products, and introduce a system of benefit to those who produce pure products on contaminated areas. It is expected that on approval of the Ukrainian Parliament it will became a new basis for reviewing of the Chernobyl Laws. The Laws and regulations of Ukraine on radiation protection are on the way to meet international basic safety standards. But there is no experience in the world of dealing with the consequences of such a wide-scale radiation catastrophe. Taking into account the fact that a certain part of the Ukrainian population have to live permanently on the radioactively

  5. Radiological error: analysis, standard setting, targeted instruction and teamworking

    International Nuclear Information System (INIS)

    FitzGerald, Richard

    2005-01-01

    Diagnostic radiology does not have objective benchmarks for acceptable levels of missed diagnoses [1]. Until now, data collection of radiological discrepancies has been very time consuming. The culture within the specialty did not encourage it. However, public concern about patient safety is increasing. There have been recent innovations in compiling radiological interpretive discrepancy rates which may facilitate radiological standard setting. However standard setting alone will not optimise radiologists' performance or patient safety. We must use these new techniques in radiological discrepancy detection to stimulate greater knowledge sharing, targeted instruction and teamworking among radiologists. Not all radiological discrepancies are errors. Radiological discrepancy programmes must not be abused as an instrument for discrediting individual radiologists. Discrepancy rates must not be distorted as a weapon in turf battles. Radiological errors may be due to many causes and are often multifactorial. A systems approach to radiological error is required. Meaningful analysis of radiological discrepancies and errors is challenging. Valid standard setting will take time. Meanwhile, we need to develop top-up training, mentoring and rehabilitation programmes. (orig.)

  6. A methodology for the estimation of the radiological consequences of a Loss of Coolant Accident

    Energy Technology Data Exchange (ETDEWEB)

    Kereszturi, Andras; Brolly, Aron; Panka, Istvan; Pazmandi, Tamas; Trosztel, Istvan [Hungarian Academy of Sciences, Budapest (Hungary). MTA EK, Centre for Energy Research

    2017-09-15

    For calculation of the radiological consequences of Large Break Loss of Coolant (LBLOCA) events, a set of various computer codes modeling the corresponding physical processes, disciplines and their appropriate subsequent data exchange are necessary. For demonstrating the methodology applied in MTA EK, a LBLOCA event at shut down reactor state - when only limited configuration of the Emergency Core Cooling System (ECCS) is available - was selected. In this special case, fission gas release from a number of fuel pins is obtained from the analyses. This paper describes the initiating event and the corresponding thermal hydraulic calculations and the further physical processes, the necessary models and computer codes and their connections. Additionally the applied conservative assumptions and the Best Estimate Plus Uncertainty (B+U) evaluation applied for characterizing the pin power and burnup distribution in the core are presented. Also, the fuel behavior processes. Finally, the newly developed methodology to predict whether the fuel pins are getting in-hermetic or not is described and the the results of the activity transport and dose calculations are shown.

  7. 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)

  8. General situation of the radiological consequences of the Chernobyl accident in Ukraine

    International Nuclear Information System (INIS)

    Grodzinsky, D.M.

    1998-01-01

    Following the Chernobyl Nuclear Accident on April 26, 1986, epidemiological analyses of data point to impressive deterioration of the health of the people affected by radionuclide contamination in the environment. This deterioration of population health embraces a broad spectrum of diseases. Epidemiological prediction of the rate of thyroid cancer in children near Chernobyl seems strikingly compatible with a real increase. But there is a tendency to consider the morbidity augmentation as a result having been associated with the factors of non-radioactive origin (chemical compounds, heavy metals and mainly social-psychological syndrome development). The Chernobyl catastrophe has implied a heavy burden for Ukraine: pollution of air, water, soils and vegetation in all ecosystems, late radiological effects in the health of people, losses of arable land and forest, necessity of mass-evacuation from thousands of settlements in the contaminated regions, severe psychological shock for millions of people, and painful suffering of unexpected life tragedies. Eleven years after, this tragic event with its causes and consequence brings one to very important conclusions concerning moral aspects of human relations within the nuclear society, as well as interactions between the society and the environment. (J.P.N.)

  9. A dynamic food-chain model and program for predicting the radiological consequences of nuclear accident

    International Nuclear Information System (INIS)

    Hu Erbang; Gao Zhanrong; Zhang Heyuan; Wei Weiqiang

    1996-12-01

    A dynamic food-chain model and program, DYFOM-95, for predicting the radiological consequences of nuclear accident has been developed, which is not only suitable to the West food-chain but also to Chinese food chain. The following processes, caused by accident release which will make an impact on radionuclide concentration in the edible parts of vegetable are considered: dry and wet deposition interception and initial retention, translocation, percolation, root uptake and tillage. Activity intake rate of animals, effects of processing and activity intake of human through ingestion pathway are also considered in calculations. The effects of leaf area index LAI of vegetable are considered in dry deposition model. A method for calculating the contribution of rain with different period and different intensity to total wet deposition is established. The program contains 1 main code and 5 sub-codes to calculate dry and wet deposition on surface of vegetable and soil, translocation of nuclides in vegetable, nuclide concentration in the edible parts of vegetable and in animal products and activity intake of human and so on. (24 refs., 9 figs., 11 tabs.)

  10. 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.)

  11. 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.

  12. Review, analysis and report on the radiological consequences resulting from accidents and incidents involving radioactive materials during transport in the period 1975-1986 by and within member states of the european communities

    International Nuclear Information System (INIS)

    Lombard, J.; Ringot, C.; Tomachevsky, E.; Hughes, J.S.; Shaw, K.B.

    1990-01-01

    Radioactive materials are routinely transported throughout the European Communities, by all modes of transport. These shipments occur in accordance with comprehensive regulations and the vast majority of these shipments are made without incident. Occasionally however accidents and other incidents have occurred at various stages of transport operations and the purpose of this study was to examine the available information on events that occurred within the Communities during the years 1975 to 1986. The information was gathered from Member States' Competent Authorities and other organisations, using a questionnaire. Most of the detailed information came from the two countries carrying out the study, the UK and France. The information gathered covered many different types of event involving a wide range of materials: it is concluded that under-reporting is a major source of uncertainty in the results. Therefore, it is emphasised that care should be used in comparisons between the results for different types of transport operations, since accidents and incidents involving certain types of transport are more fully reported than others. Consequently, the authors stress the need for improved reporting and recording procedures. No evidence was found of any major health consequences resulting from the accidents and incidents studied. However, there were instances of high doses having been received by workers, mainly as a result of inadequate preparation of packages prior to despatch. These events point to the need to maintain high standards of quality assurance at all stages of transport operations

  13. Decontamination analysis of a radiologically contaminated site

    International Nuclear Information System (INIS)

    Tawil, J.J.; Strenge, D.L.

    1984-02-01

    This paper presents an analysis of decontamination options at the NUWAZX-83 exercise site. Held in May 1983, the purpose of the exercise was to evaluate the ability of federal, state and local officials to respond to a radiological accident involving nuclear weapons. A computer program developed by Pacific Northwest Laboratory was used to conduct the decontamination analysis. The program, called DECON, was designed to assist personnel engaged in the planning of decontamination activities. The many features of DECON that are demonstrated in this paper contribute to its potential usefulness as a planning tool for site restoration. Strategies that are analyzed with DECON include: (1) using a Quick-Vac option, under which exterior surfaces are vacuumed before it rains; (2) protecting surfaces against precipitation; (3) prohibiting specific operations on selected surfaces; (4) requiring that specific methods be used on selected surfaces; (5) evaluating the trade-off between cleanup standards and decontamination costs; and (6) varying clean-up standards according to expected human exposure to the surface

  14. 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

  15. Tank waste compositions and atmospheric dispersion coefficients for use in accelerated safety analysis consequence assessments. Revision 1

    International Nuclear Information System (INIS)

    Savino, A.V.

    1995-11-01

    This topical report contains technical support information used to determine accident consequences for the Tank Farms Accelerated Safety Analysis (ASA) Interim Chapter 3, Hazard and Accident Analysis: Potential for Releases and Required Mitigation and Prevention and the Tank Waste Remediation System (TWRS) environmental impact statement (EIS) accident consequence report. It does not determine accident consequences or describe specific accident scenarios, but instead provides generic information used to calculate radiological and toxic chemical consequences for postulated tank farms accident releases

  16. 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

  17. 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

  18. Job Aids for Using Preventive Radiological/Nuclear Detection Equipment for Consequence Management

    Energy Technology Data Exchange (ETDEWEB)

    Buddemeier, Brooke R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Haynes, Daniel [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Wood-Zika, Annmarie R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Klemic, Gladys [US Department of Homeland Security National Urban

    2017-10-02

    The overall objective of this project is to research, evaluate, and test first responder preventive radiological/nuclear detection equipment (PRND) to provide state and local agencies with guidance on how to best use this equipment for response after a radiological/nuclear release or detonation.

  19. Medical radiological consequences of the Chernobyl catastrophe in Russia. Estimation of radiation risks

    International Nuclear Information System (INIS)

    Ivanov, V.; Tsyb, A.; Ivanov, S.; Pokrovsky, V.

    2004-01-01

    The Chernobyl accident, one of the worst radiation-related disasters ever, occurred about 18 year ago. A lot has been done over the past years to mitigate the consequences of this accident, especially in the worst affected territories of Belarus, Russia and Ukraine. The efforts to study health effects of the accident, however, need to be continued for many years to come, being an integral part of developing a general strategy for dealing with long-term effects. The question now arises: To what extent health consequences could be evaluated in 1986, given the existing scientific base of radiation epidemiology? The latest 20-30 years have seen a rapid development of radiation epidemiology, which was brought about, first of all, by the need to analyze long-term radiation effects of the 1945 atomic bombing in Hiroshima and Nagasaki. It may now be considered as proved that high and medium radiation doses (above 0.3 Sv) lead to an increase in cancer incidence rates. Based on the Japanese data, the ICRP proposed mathematical models to be used for predicting long-term effects of radiation exposure. This brings up a question: Are radiation risks derived for Hiroshima and Nagasaki applicable to low doses (0.2 Sv)? An answer is critically important, as the overwhelming majority of emergency workers and the population exposed as a result of the Chernobyl accident received doses within this range. Actually, understanding of these issues is crucial for dealing with long-term radiation effects of the Chernobyl accident. Deriving radiation risk factors for the Japanese cohort with medium and high doses was based on large-scale epidemiological studies of 86.5 thousand people during a prolonged period. As of now, no other approaches exist to estimating long-term radiation effects. Following the Chernobyl accident the All-Union Distributed Registry of persons exposed to radiation was established as soon as in the summer 1986. The Research Institute of Medical Radiology (Medical

  20. Cost-benefit analysis in decision making for diagnostic radiology

    International Nuclear Information System (INIS)

    Fabrikant, J.I.; Hilberg, A.W.

    1982-02-01

    This paper reviews certain current concepts and methods relating to benefit-risk analysis, in terms of economic costs and raidation risks to health, in relation to the benefits from diagnostic radiology in clinical medicine

  1. An assessment of the radiological consequences of releases to groundwater following a core-melt accident at the Sizewell PWR

    International Nuclear Information System (INIS)

    Maul, P.R.

    1984-03-01

    In the extremely unlikely event of a degraded core accident at the proposed Sizewell PWR it is theoretically possible for the core to melt through the containment, after which activity could enter groundwater directly or as a result of subsequent leaching of the core in the ground. The radiological consequences of such an event are analysed and compared with the analysis undertaken by the NRPB for the corresponding releases to atmosphere. It is concluded that the risks associated with the groundwater route are much less important than those associated with the atmospheric route. The much longer transport times in the ground compared with those in the atmosphere enable countermeasures to be taken, if necessary, to restrict doses to members of the public to very low levels in the first few years following the accident. The entry of long-lived radionuclides into the sea over very long timescales results in the largest contribution to population doses, but these are delivered at extremely low dose rates which would be negligible compared with background exposure. (author)

  2. 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

  3. Radiological and dosimetric consequences in case of nuclear accident: taking them into account within the security approach and protection challenges

    International Nuclear Information System (INIS)

    Cogez, E.; Herviou, K.; Isnard, O.; Cessac, B.; Reales, N.; Quentric, E.; Quelo, D.

    2010-01-01

    This report first proposes a presentation of the 'defence in depth' concept which comprises five as much as possible independent levels: preventing operation anomalies and system failures, maintaining the installation within the authorized domain, controlling accidents within design hypotheses, preventing the degradation of accidental conditions and limiting consequences of severe accidents, limiting radiological consequences for population in case of important releases. Then, after a description of a release atmospheric dispersion and of its consequences, this report describes the consequences of two accident scenarios. The first accident is a failure of steam generator tubes, and the second a loss of primary coolant. It notably indicates the main released radionuclides, exposure levels at different distance for a given set of dispersion conditions

  4. Consequence Analysis of the MHTGR and PBMR

    International Nuclear Information System (INIS)

    Jeong, Jong Tae; Yang, Joon Eon; Lee, Won Jae

    2006-01-01

    The probabilistic safety assessment of the VHTR design provides a systematic analysis to identify and quantify all risks that the plant imposes to the operators, general public, and the environment and thus demonstrates compliance to regulatory risk criteria. During the preliminary conceptual design of VHTR in Korea, both block- and pebble type-fuel are considered. Therefore, the consequence analysis of VHTR using both types of fuel were made in order to obtain the basic insights for the classification of events and the formation of the PSA framework of the VHTR

  5. The effects of actinide separation on the radiological consequences of geologic disposal of high-level waste

    International Nuclear Information System (INIS)

    Hill, M.D.; White, I.F.; Fleishman, A.B.

    1980-01-01

    It has often been suggested that the potential hazard to man from the disposal of high-level radioactive waste could be reduced by removing a substantial fraction of the actinide elements. In this report the effects of actinide separation on the radiological consequences of one of the disposal options currently under consideration, that of burial in deep geologic formations, are examined. The results show that the potential radiological impact of geologic disposal of high-level waste arises from both long-lived fission products and actinides (and their daughter radionuclides). Neither class of radionuclides is of overriding importance and actinide separation would therefore reduce the radiological impact to only a limited extent and over limited periods. There might be a case for attempting to reduce doses from 237 Np. To achieve this it appears to be necessary to separate both neptunium and its precursor element americium. However, there are major uncertainties in the data needed to predict doses from 237 Np; further research is required to resolve these uncertainties. In addition, consideration should be given to alternative methods of reducing the radiological impact of geologic disposal. The conclusions of this assessment differ considerably from those of similar studies based on the concept of toxicity indices. Use of these indices can lead to incorrect allocation of research and development effort. (author)

  6. PERSPECTIVES ON A DOE CONSEQUENCE INPUTS FOR ACCIDENT ANALYSIS APPLICATIONS

    International Nuclear Information System (INIS)

    O'Kula, K.R.; Thoman, D.C.; Lowrie, J.; Keller, A.

    2008-01-01

    Department of Energy (DOE) accident analysis for establishing the required control sets for nuclear facility safety applies a series of simplifying, reasonably conservative assumptions regarding inputs and methodologies for quantifying dose consequences. Most of the analytical practices are conservative, have a technical basis, and are based on regulatory precedent. However, others are judgmental and based on older understanding of phenomenology. The latter type of practices can be found in modeling hypothetical releases into the atmosphere and the subsequent exposure. Often the judgments applied are not based on current technical understanding but on work that has been superseded. The objective of this paper is to review the technical basis for the major inputs and assumptions in the quantification of consequence estimates supporting DOE accident analysis, and to identify those that could be reassessed in light of current understanding of atmospheric dispersion and radiological exposure. Inputs and assumptions of interest include: Meteorological data basis; Breathing rate; and Inhalation dose conversion factor. A simple dose calculation is provided to show the relative difference achieved by improving the technical bases

  7. The radiological consequences of notional accidental releases of radioactivity from fast breeder reactors: the influence of the meteorological conditions

    International Nuclear Information System (INIS)

    Hemming, C.R.; Hallam, J.; Kelly, G.N.

    1980-04-01

    The radiological consequences of a wide range of notional accidental releases from a 1300 MW(e) LMFBR (liquid Metal-cooled Fast Breeder Reactor) were assessed in a previous study by the National Radiological Protection Board. In the present study the sensitivity of the predicted consequences to the meteorological conditions was investigated. The influence of the wind direction, and hence the distribution of the exposed population, and of atmospheric stability at the time of the release are considered separately. Conclusions are reached on the precision required in specifying atmospheric stability conditions to estimate reliably the distribution of possible consequences following a given release of activity. The probability distributions of consequences for selected releases from two locations are evaluated taking account of the frequency distribution of wind direction and atmospheric stability at each location. The variation is large and demonstrates the importance of taking account of the whole range of meteorological conditions when assessing the risk presented by an accidental release of activity. (author)

  8. Transporting radioactive materials and possible radiological consequences from accidents as might be seen by medical institutions

    International Nuclear Information System (INIS)

    Jefferson, R.M.

    1990-01-01

    This paper discusses how medical personnel faced with treating victims of an accident involving radioactive material should be suspicious concerning possible radiological involvement. At the same time, they should be careful to obtain the necessary information in order to make a rational decision as to the likelihood of such involvement. Having made that decision, it is entirely possible then to approach the problem from a medical standpoint in such a way as to determine the extent of radiological involvement and to apply proper medical treatment consistent with that exposure

  9. Chemical, Biological, Radiological, Nuclear, and High-Yield Explosives Consequences Management

    Science.gov (United States)

    2006-10-02

    protective measures associated with such offensive operations. Since riot control agents and herbicides are not considered to be chemical warfare agents...control. Procedures to avoid, reduce, remove, or render harmless (temporarily or permanently) nuclear, radiological, biological, and chemical...destroying, neutralizing, making harmless , or removing chemical or biological agents, or by removing radioactive material clinging to or around it. (JP 1

  10. 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

  11. 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.

  12. 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

  13. Multi-criteria analysis for evaluating the radiological and ecological safety measures in radioactive waste management

    International Nuclear Information System (INIS)

    Sazykina, T.G.; Kryshev, I.I.

    2006-01-01

    A methodological approach is presented for multicriterial evaluating the effectiveness of radiation ecological safety measures during radioactive waste management. The approach is based on multicriterial analysis with consideration of radiological, ecological, social, economical consequences of various safety measures. The application of the multicriterial approach is demonstrated taking as an example of decision-making on the most effective actions for rehabilitation of a water subject, contaminated with radionuclides [ru

  14. Rapid and reliable predictions of the radiological consequences of accidents as an aid to decisions on countermeasures

    International Nuclear Information System (INIS)

    Kelly, G.N.

    1990-01-01

    The rapid and reliable assessment of the potential radiological consequences of an accident at a nuclear installation is an essential input to timely decisions on the effective introduction of countermeasures. There have been considerable improvements over the past decade or so in the methods used for such assessments and, in particular, in the development of computerized systems. The need for such systems is described, together with their current state of development and possible future trends. This topic has featured prominently within the CEC's Radiation Protection Research Programme and is likely to do so far the foreseeable future. The main features of this research, its achievements to date and future directions are described

  15. Evaluation of atmospheric dispersion/consequence models supporting safety analysis

    International Nuclear Information System (INIS)

    O'Kula, K.R.; Lazaro, M.A.; Woodard, K.

    1996-01-01

    Two DOE Working Groups have completed evaluation of accident phenomenology and consequence methodologies used to support DOE facility safety documentation. The independent evaluations each concluded that no one computer model adequately addresses all accident and atmospheric release conditions. MACCS2, MATHEW/ADPIC, TRAC RA/HA, and COSYMA are adequate for most radiological dispersion and consequence needs. ALOHA, DEGADIS, HGSYSTEM, TSCREEN, and SLAB are recommended for chemical dispersion and consequence applications. Additional work is suggested, principally in evaluation of new models, targeting certain models for continued development, training, and establishing a Web page for guidance to safety analysts

  16. [Digitalization of radiological imaging information and consequences for patient care in the hospital ].

    Science.gov (United States)

    den Heeten, G J; Barneveld Binkhuysen, F H

    2001-08-25

    Determining the rate at which radiology must be digitalised has been a controversial issue for many years. Much radiological information is still obtained from the film-screen combination (X-rays) with all of its known inherent restrictions. The importance of imaging information in the healthcare process continues to increase for both radiologists and referring physicians, and the ongoing developments in information technology means that it is possible to integrate imaging information and electronic patient files. The healthcare process can only become more effective and efficient when the appropriate information is in the right place at the right time, something that conventional methods, using photos that need to be physically moved, can scarcely satisfy. There is also a desire for integration with information obtained from nuclear medicine, pathology and endoscopy, and eventually of all stand-alone data systems with relevance for the individually oriented hospital healthcare. The transition from a conventional to a digital process is complex; it is accompanied by the transition from a data-oriented to a process-oriented system. Many years have already been invested in the integration of information systems and the development of digital systems within radiology, the current performance of which is such that many hospitals are considering the digitalisation process or are already implementing parts of it.

  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. The radiological consequences of degraded core accidents for the Sizewell PWR The impact of adopting revised frequencies of occurrence

    CERN Document Server

    Kelly, G N

    1983-01-01

    The radiological consequences of degraded core accidents postulated for the Sizewell PWR were assessed in an earlier study and the results published in NRPB-R137. Further analyses have since been made by the Central Electricity Generating Board (CEGB) of degraded core accidents which have led to a revision of their predicted frequencies of occurrence. The implications of these revised frequencies, in terms of the risk to the public from degraded core accidents, are evaluated in this report. Increases, by factors typically within the range of about 1.5 to 7, are predicted in the consequences, compared with those estimated in the earlier study. However, the predicted risk from degraded core accidents, despite these increases, remains exceedingly small.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-11-01

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

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

    International Nuclear Information System (INIS)

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

    1995-11-01

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

  1. Probabilistic safety analysis and radiological protection

    International Nuclear Information System (INIS)

    Guimaraes, A.C.F.; Goes, A.G.A.

    1990-05-01

    The author presents a brief description of NUREG-1150 and NUREG-0956, both documents of great importance in the risk area. Based on document's recommendations and following NUREG-1150 similar methodology, a calculation model is proposed in this publication, with the purpose of analyzing the consequences of a severe accident in Angra-I Power Station. The suggested model can be divided in two stages: the first one called front-end considers the power station system safety during the accident, and the second called back-end cares for accident consequences. 9 refs. (B.C.A.)

  2. Probabilistic consequence study of residual radiological effects from a hypothetical ten-ton inadvertent nuclear yield. Weapons Safety Program

    International Nuclear Information System (INIS)

    Harvey, T.; Peters, L.; Serduke, F.; Edwards, L.

    1994-01-01

    In this paper we study the potential radiological consequences of a strategic bomber accident, in which one of the assumed on-board nuclear weapons explodes with an arbitrarily chosen 10-ton nuclear yield. The frequency of such an occurrence is infinitesimal. The safety design features in today s nuclear weapons' systems essentially forbid its occurrence. We have a chosen a military base which has the feature of being a representative combination of urban and rural populations. The assumed ''crash site'' is near the northwest comer of the military base, close to civilian housing located just across the street from the base. A worst case wind would be from the ESE (east south east). This would cause fission debris to be dispersed toward the largest population centers and, thus, would lead to the largest Pu ''collective'' doses (i.e., a dose integrated over time and summed over individuals). Also, if an ESE wind were blowing at accident time, some people in nearby housing could receive lethal gamma-ray doses from fallout before evacuation could occur. It is assumed only one weapon undergoes nuclear yield; the other on-board weapons would HE detonate and the Pu would be aerosolized and lofted. We assume an activity-size distribution and lofting similar to those used to predict fallout measured at NTS. The main thrust of our study is to provide estimates of probabilistic radiological risks to the population local to a strategic bomber crash site. The studied radiological consequences are: cloud-passage doses from Pu inhalation; doses from groundshine due to gamma-producing radionuclides; and areal contamination from Pu and the long-lived fission products Cs-137 and Sr-90

  3. 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)

  4. The potential for reducing the radiological consequences of reactor decommissioning through selection of construction materials for activated components

    International Nuclear Information System (INIS)

    Woollam, P.B.

    1984-08-01

    This report considers whether it may be possible to reduce the radiological consequences of reactor decommissioning by careful attention to the specification of the elemental concentration of materials used in the reactor's construction. In particular, consideration is given to the potential for reduction of the concentration of elements known to activate to long lived daughter isotopes. Two particular areas are addressed, both applied to Sizewell 'B' PWR. The first is the choice of raw materials for the construction of the concrete bioshield to minimise future waste arisings. The second is the specification of some trace element concentrations in the steel pressure vessel and reactor internal structures to minimise personnel exposure at decommissioning time. The report presents extensive analyses of many of the candidate raw materials for Sizewell 'B' concrete, including PFA, and derives the radiological consequences for the eventual disposal of these materials to a hypothetical municipal land fill waste site. Data are also presented on the concentrations of important elements activating to gamma emitting daughters in type 304 stainless steels, leading to an assessment of likely dose equivalent rates at decommissioning time from the pressure vessel and from the internal components. (author)

  5. Strategic Aspects of Nuclear and Radiological Emergency Management. Planning for Effective Decision Making; Consequence Management and Transition to Recovery

    International Nuclear Information System (INIS)

    2010-01-01

    The collective experience of the NEA Working Party on Nuclear Emergency Matters (WPNEM), and in particular, the experience from the International Nuclear Emergency Exercise (INEX) series, has shown that it is important to plan and to implement emergency response actions based on a guiding strategic vision. Within this context, Strategic Aspects of Nuclear and Radiological Emergency Management presents a framework of strategic planning elements to be considered by national emergency management authorities when establishing or enhancing processes for decision making, and when developing or implementing protection strategies. The focus is on nuclear or radiological emergency situations leading to complex preparedness and response conditions, involving multiple jurisdictions and significant international interfaces. The report is aimed at national emergency management authorities, international organisations and those who are seeking to improve the effectiveness of emergency management. Its goal is to provide insights into decision-making processes within existing emergency planning arrangements. It also highlights common areas of good practice in decision making. Specific areas for improvement, identified during the INEX-3 consequence management exercise, are included, particularly in support of decision making for countermeasures for consequence management and the transition to recovery. (authors)

  6. Summaries of studies carried out in the NKS/BOK-2 project. Technical report[Radiological and environmental consequences

    Energy Technology Data Exchange (ETDEWEB)

    Palsson, S E [Icelandic Radiation Protection Inst., Reykjavik (Iceland)

    2002-12-01

    Summaries of studies carried out in the NKSBOK-2 project, Radiological and Environmental Consequences. The structure of the project as such is described in NKS-64, Radiological and Environmental Consequences - Final Report of the Nordic Nuclear Safety Research Project BOK-2. That report also includes compilations based on the summaries presented in this report. The project was carried out 1998-2001 with participants from all the Nordic countries. Representatives from the Baltic States were also invited to some of the meetings and seminars. The project consisted of work on terrestrial and marine radioecology and had a broad scope in order to enable participation of research groups with various fields of interest. The topics included improving assessment of old and recent fallout, use of radionuclides as tracers in Nordic marine areas, improving assessment of internal doses and use of mass spectrometry in radioecology. This report is a compilation of summaries from each research group, 32 papers in all, and gives references to papers published in scientific journals. Some of the studies have been described previously, at least to some degree, in NKS-70, Proceedings of the 8{sup th} Nordic Seminar on Radioecology, 25-28 February 2001, Rovaniemi, Finland. (au)

  7. Assessment Of Source Term And Radiological Consequences For Design Basis Accident And Beyond Design Basis Accident Of The Dalat Nuclear Research Reactor

    International Nuclear Information System (INIS)

    Luong Ba Vien; Le Vinh Vinh; Huynh Ton Nghiem; Nguyen Kien Cuong; Tran Tri Vien

    2011-01-01

    The paper presents results of the assessment of source terms and radiological consequences for the Design Basis Accident (DBA) and Beyond Design Basis Accident (BDBA) of the Dalat Nuclear Research Reactor. The dropping of one fuel assembly during fuel handling operation leading to the failure of fuel cladding and the release of fission products into the environment was selected as a DBA for the analysis. For the BDBA, the introduction of a step positive reactivity due to the falling of a heavy block from the rotating bridge crane in the reactor hall onto a part of the platform where are disposed the control rod drives is postulated. The result of the radiological consequence analyses shows that doses to members of the public are below annual dose limit for both DBA and BDBA events. However, doses from exposure to operating staff and experimenters working inside the reactor hall are predicted to be very high in case of BDBA and therefore the protective actions should be taken when the accident occurs. (author)

  8. The radiological accident of Goiania and its consequences for the development of law

    International Nuclear Information System (INIS)

    Franco, N.M.F.L.

    1998-01-01

    The radiological accident of Goiania and its repercussions caused intense debate in Brazilian society, which extended to the legislative sphere. One of the principal outcomes of this debate was the inclusion in the new Brazilian Constitutional Charter of legal provisions covering the control of nuclear energy and of radiation sources. Internationally, the 1986 Vienna Convention on Early Notification of a Nuclear Accident and the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency were invoked following the accident and proved to be effective in facilitating international co-operation and solidarity to deal with the aftermath of the accident. A number of international treaties on assistance in the event of nuclear accidents, the management of radioactive waste and the management of spent fuel are currently in force. The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste, adopted in 1997, is the most recent treaty promoting the sustainability of nuclear activities. Looking ahead, an international legal framework is needed to build upon and improve the principles of a culture of radiation safety. (author)

  9. Data analysis for radiological characterisation: Geostatistical and statistical complementarity

    International Nuclear Information System (INIS)

    Desnoyers, Yvon; Dubot, Didier

    2012-01-01

    Radiological characterisation may cover a large range of evaluation objectives during a decommissioning and dismantling (D and D) project: removal of doubt, delineation of contaminated materials, monitoring of the decontamination work and final survey. At each stage, collecting relevant data to be able to draw the conclusions needed is quite a big challenge. In particular two radiological characterisation stages require an advanced sampling process and data analysis, namely the initial categorization and optimisation of the materials to be removed and the final survey to demonstrate compliance with clearance levels. On the one hand the latter is widely used and well developed in national guides and norms, using random sampling designs and statistical data analysis. On the other hand a more complex evaluation methodology has to be implemented for the initial radiological characterisation, both for sampling design and for data analysis. The geostatistical framework is an efficient way to satisfy the radiological characterisation requirements providing a sound decision-making approach for the decommissioning and dismantling of nuclear premises. The relevance of the geostatistical methodology relies on the presence of a spatial continuity for radiological contamination. Thus geo-statistics provides reliable methods for activity estimation, uncertainty quantification and risk analysis, leading to a sound classification of radiological waste (surfaces and volumes). This way, the radiological characterization of contaminated premises can be divided into three steps. First, the most exhaustive facility analysis provides historical and qualitative information. Then, a systematic (exhaustive or not) surface survey of the contamination is implemented on a regular grid. Finally, in order to assess activity levels and contamination depths, destructive samples are collected at several locations within the premises (based on the surface survey results) and analysed. Combined with

  10. Radiologic analysis of congenital limb anomalies

    International Nuclear Information System (INIS)

    Chung, Hong Jun; Kim, Ok Hwa; Shinn, Kyung Sub; Kim, Nam Ae

    1994-01-01

    Congenital limb anomalies are manifested in various degree of severity and complexity bearing conclusion for description and nomenclature of each anomaly. We retrospectively analyzed the roentgenograms of congenital limb anomalies for the purpose of further understanding of the radiologic manifestations based on the embryonal defect and also to find the incidence of each anomaly. Total number of the patients was 89 with 137 anomalies. Recently the uniform system of classification for congenital anomalies of the upper limb was adopted by International Federation of Societies for Surgery of the Hand (IFSSH), which were categorized as 7 classifications. We used the IFSSH classification with some modification as 5 classifications; failure of formation of parts, failure of differentiation of parts, duplications, overgrowth and undergrowth. The patients with upper limb anomalies were 65 out of 89(73%), lower limb were 21(24%), and both upper and lower limb anomalies were 3(4%). Failure of formation was seen in 18%, failure of differentiation 39%, duplications 39%, overgrowth 8%, and undergrowth in 12%. Thirty-five patients had more than one anomaly, and 14 patients had intergroup anomalies. The upper limb anomalies were more common than lower limb. Among the anomalies, failure of differentiation and duplications were the most common types of congenital limb anomalies. Patients with failure of formation, failure of differentiation, and undergrowth had intergroup association of anomalies, but duplication and overgrowth tended to be isolated anomalies

  11. 100 classic papers of interventional radiology: A citation analysis.

    Science.gov (United States)

    Crockett, Matthew T; Browne, Ronan Fj; MacMahon, Peter J; Lawler, Leo

    2015-04-28

    To define the 100 citation classic papers of interventional radiology. Using the database of Journal Citation Reports the 40 highest impact factor radiology journals were chosen. From these journals the 100 most cited interventional radiology papers were chosen and analysed. The top paper received 2497 citations and the 100(th) paper 200 citations. The average number of citations was 320. Dates of publication ranged from 1953 - 2005. Most papers originated in the United States (n = 67) followed by Italy (n = 20) and France (n = 10). Harvard University (n = 18) and Osped Civile (n = 11) were the most prolific institutions. Ten journals produced all of the top 100 papers with "Radiology" and "AJR" making up the majority. SN Goldberg and T Livraghi were the most prolific authors. Nearly two thirds of the papers (n = 61) were published after 1990. This analysis identifies many of the landmark interventional radiology papers and provides a fascinating insight into the changing discourse within the field. It also identifies topics, authors and institutions which have impacted greatly on the specialty.

  12. Knowledge based analysis of radiology reports using conceptual graphs

    International Nuclear Information System (INIS)

    Schroeder, M.

    1992-07-01

    The telegraphic language found in radiological reports can be well understood by a natrual language system using the underlying domain knowledge. We present the METEXA system, which emphasizes the use of radiological domain knowledge to determine the semantics of utterances. Syntactic and semantic analysis, lexical sematics and the structure of the domain model are described in some detail. A resolution-based inference engine answers relevant questions concerning the contents of the reports. As knowledge representation formalism the Conceptual Graph Theory by John Sowa has been chosen. (orig.)

  13. 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

  14. AP600 containment purge radiological analysis

    Energy Technology Data Exchange (ETDEWEB)

    O`Connor, M.; Schulz, J.; Tan, C. [Bechtel Power Corporation (United States)] [and others

    1995-02-01

    The AP600 Project is a passive pressurized water reactor power plant which is part of the Design Certification and First-of-a-Kind Engineering effort under the Advanced Light Water Reactor program. Included in this process is the design of the containment air filtration system which will be the subject of this paper. We will compare the practice used by previous plants with the AP600 approach to meet the goals of industry standards in sizing the containment air filtration system. The radiological aspects of design are of primary significance and will be the focus of this paper. The AP600 Project optimized the design to combine the functions of the high volumetric flow rate, low volumetric flow rate, and containment cleanup and other filtration systems into one multi-functional system. This achieves a more simplified, standardized, and lower cost design. Studies were performed to determine the possible concentrations of radioactive material in the containment atmosphere and the effectiveness of the purge system to keep concentrations within 10CFR20 limits and within offsite dose objectives. The concentrations were determined for various reactor coolant system leakage rates and containment purge modes of operation. The resultant concentrations were used to determine the containment accessibility during various stages of normal plant operation including refueling. The results of the parametric studies indicate that a dual train purge system with a capacity of 4,000 cfm per train is more than adequate to control the airborne radioactivity levels inside containment during normal plant operation and refueling, and satisfies the goals of ANSI/ANS-56.6-1986 and limits the amount of radioactive material released to the environment per ANSI/ANS 59.2-1985 to provide a safe environment for plant personnel and offsite residents.

  15. The regulatory consequences of Publication 60 of the ICRP (International Commission on Radiological Protection)

    International Nuclear Information System (INIS)

    Sugier, Annie

    1992-01-01

    The system of radiological protection recommended by the ICRP for future and existing proposed and continuing practices is based on the following general principles: justification, optimisation and limitation of exposure levels. This means that no practice involving exposures to radiation should be adopted unless it produces sufficient benefit to the exposed individuals or to the society to offset the radiation detriment it causes. In relation to any particular source within a practice, the magnitude of individual doses, the number of people exposed, and the likelihood of incurring exposures where these are not certain to be received should all be kept as low as reasonably achievable, economic and social factors being taken into account. The exposure of individuals resulting from the combination of all the relevant practices should be subject to dose limits, or to some control of risk in the case of potential exposures. The system for radiological protection and the values of the limits associated with it, are related the state of knowledge of the effects of radiation. This explains the periodic revision of the corresponding regulatory texts. In a field of such complexity, concerned by disciplines as diverse as medicine, biology, chemistry, statistics, etc., the question naturally arises as to which authority has the capacity to determine an agreed policy. As far as the European Community is concerned, the basic standards related to radiation protection are the subject of Directives which have to be incorporated into national laws by each member state. These directives are under review taking into account explicitly the ICRP recommendations. International agencies whose mission is concerned with the effects of ionising radiation, publish also basic standards related to radiological protection which are not imposed to the participating states except when they collaborate with those bodies, and which mainly act as international references. Such norms also comply with

  16. Analysis of a radiation incident with intraoral dental radiological equipment

    International Nuclear Information System (INIS)

    Malone, J.F.

    1996-01-01

    A case is described involving a serious incident with dental radiological equipment, containing many lessons that may be applied to the preparation of other cases. The description includes an account of the incident, the circumstances surrounding it, the dosimetry, risk estimates and the medical consequences of the incident. In addition, some aspects of the associated legal proceedings are reviewed and assessed. As a result of the incident described, a number of conclusions are drawn with respect to important practices in ensuring the safety of installations and the value of evidence brought forward by expert witnesses. (author)

  17. Risks and consequences of a hypothetical radiological accident on nuclear powered submarine traversing Suez canal

    International Nuclear Information System (INIS)

    Salama, Mohamed

    2008-01-01

    Full text: Egypt has unique problem in Suez Canal, although there are, a number of radioactive Cargos traveling through the Canal which includes new and spent reactor fuel and about 100 metric tons of uranium hexafluoride each year, under the regulatory control of the Egyptian Atomic Energy Authority, there is, still a major problem concerning the passage of a number of nuclear powered vessels and submarines passing through the canal several times each year. The passage of these vessels and submarines has a political situation and not under the regulatory control of the Egyptian regulatory body. In spite of all precautions that are taken, in the nuclear powered vessels and submarines from the point of view of the rugged design of the reactor plant, multiple safety systems and operation with exceptional consideration for safety. Although of all of these a potential for a serious accident may does arise, even though, its probability is minimal. The Government of Egypt has established a national radiological emergency plan in order to cope with any radiological accidents, which may arise inside the country. Suez Canal lies in the north east of Egypt, and passes through a zone of considerable business, agriculture and industrial activities. The zone consists of three populated provinces, Port Said, Ismailia and Suez. According to Suez Canal authority regulations it is not allowed for these vessels and submarines to be landed in port. The motivation of the present paper was undertaken to discuss a hypothetical nuclear reactor accident aboard a nuclear powered submarine occurred during its passage in the Suez Canal. Such an accident will produce a radioactive cloud containing a number of radioactive materials. In such type of accidents contamination and causality zones, could extend to several kilometers. The different phases of the accident are going to be discussed and analyzed. The emergency actions taken during the accident phases are going to be presented. The

  18. Open Access Journal Policies: A Systematic Analysis of Radiology Journals.

    Science.gov (United States)

    Narayan, Anand; Lobner, Katie; Fritz, Jan

    2018-02-01

    The open access movement has pushed for greater access to scientific knowledge by expanding access to scientific journal articles. There is limited information about the extent to which open access policies have been adopted by radiology journals. We performed a systematic analysis to ascertain the proportion of radiology journals with open access options. A search was performed with the assistance of a clinical informationist. Full and mixed English-language diagnostic and interventional radiology Web of Science journals (impact factors > 1.0) were included. Nuclear medicine, radiation oncology, physics, and solicitation-only journals were excluded. Primary outcome was open access option (yes or no) with additional outcomes including presence or absence of embargo, complete or partial copyright transfer, publication fees, and self-archiving policies. Secondary outcomes included journal citations, journal impact factors, immediacy, Eigenfactor, and article influence scores. Independent double readings were performed with differences resolved by consensus, supplemented by contacting editorial staff at each journal. In all, 125 journals were identified; review yielded 49 journals (39%, mean impact factor of 2.61). Thirty-six of the journals had open access options (73.4%), and four journals were exclusively open access (8.2%). Twelve-month embargoes were most commonly cited (90.6%) with 28.6% of journals stating that they did not require a complete transfer of copyright. Prices for open access options ranged from $750 to $4,000 (median $3,000). No statistically significant differences were found in journal impact measures comparing journals with open access options to journals without open access options. Diagnostic and interventional radiology journals have widely adopted open access options with a few radiology journals being exclusively open access. Copyright © 2017 American College of Radiology. Published by Elsevier Inc. All rights reserved.

  19. 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

  20. Environmental impacts of radiological consequences during the anticipated transients without scram (ATWS) events in nuclear power reactors

    International Nuclear Information System (INIS)

    El-Kafas, A.A.

    2011-01-01

    Anticipated transients without scram (ATWS), is one of the (worst case) accidents could happen if the system that provides a highly reliable means of shutting down the reactor (scram system )fails to work during a reactor event (anticipated transient).It has two general characteristics: (1) Initiation by a transient anticipated to occur one or more times in the life of reactor and ,(2) Assumed to proceed without scram.The types of events considered are those used for designing the plant .The evaluation of the radiological consequences during the assessment of the nuclear events,especially ATWS in nuclear power reactors, is very essential for environmental studies and public safety. In this paper, the root cases for nuclear events and dose calculation are presented. Scenario of accident sequences together with radiological impacts is illustrated for loss of coolant accident (LOCA) for a typical pressurized water reactor nuclear power plant. Recommendations for mitigating or preventing the release of radiation and high radioactive materials to environment are presented.

  1. Trends in the value and consequences of radiologic imaging of perforated gastroduodenal ulcer; A 50-year experience

    Energy Technology Data Exchange (ETDEWEB)

    Svanes, C.; Salvesen, H.; Larsen, T.B.; Svanes, K.; Soereide, O. (Haukeland Sykehus, Bergen (Norway))

    1990-01-01

    The trends in and value and consequences of radiologic imaging in 1128 patients with perforated gastroduodenal ulcer have been studied over the 50-year period 1935 to 1985. The proportion of patients undergoing plain X-ray studies increased from 4% in the first 5-year period (1935 to 1939) to 94% in the last (1980 to 1985). Pneumoperitoneum was found in 77% of those undergoing X-ray studies. Water-soluble contrast studies were introduced in 1960, and in the three 5-year periods 1970 to 1985 from 8% to 13% underwent such imaging. Leakage was demonstrated in 60% of those undergoing contrast studies. Contrast studies have had a limited role in the pretreatment evaluation of these patients. The frequency of pneumoperitoneum was fairly constant over the 50-year period, and the only patient characteristic that influenced the occurrence of free gas in the abdominal cavity was age, with a higher proportion of patients with pneumoperitoneum in old patients. Any radiologic study increased treatment delay by at least 2 h. 18 refs., 2 figs., 5 tabs.

  2. Preclosure radiological safety analysis for accident conditions of the potential Yucca Mountain Repository: Underground facilities

    International Nuclear Information System (INIS)

    Ma, C.W.; Sit, R.C.; Zavoshy, S.J.; Jardine, L.J.; Laub, T.W.

    1992-06-01

    This preliminary preclosure radiological safety analysis assesses the scenarios, probabilities, and potential radiological consequences associated with postulated accidents in the underground facility of the potential Yucca Mountain repository. The analysis follows a probabilistic-risk-assessment approach. Twenty-one event trees resulting in 129 accident scenarios are developed. Most of the scenarios have estimated annual probabilities ranging from 10 -11 /yr to 10 -5 /yr. The study identifies 33 scenarios that could result in offsite doses over 50 mrem and that have annual probabilities greater than 10 -9 /yr. The largest offsite dose is calculated to be 220 mrem, which is less than the 500 mrem value used to define items important to safety in 10 CFR 60. The study does not address an estimate of uncertainties, therefore conclusions or decisions made as a result of this report should be made with caution

  3. 40 CFR 68.22 - Offsite consequence analysis parameters.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 15 2010-07-01 2010-07-01 false Offsite consequence analysis... PROGRAMS (CONTINUED) CHEMICAL ACCIDENT PREVENTION PROVISIONS Hazard Assessment § 68.22 Offsite consequence analysis parameters. (a) Endpoints. For analyses of offsite consequences, the following endpoints shall be...

  4. Source terms; isolation and radiological consequences of carbon-14 waste in the Swedish SFR repository

    International Nuclear Information System (INIS)

    Hesboel, R.; Puigdomenech, I.; Evans, S.

    1990-01-01

    The source term, isolation capacity, and long-term radiological exposure of 14 C from the Swedish underground repository for low and intermediate level waste (SFR) is assessed. The prospective amount of 14 C in the repository is assumed to be 5 TBq. Spent ion exchange resins will be the dominant source of 14 C. The pore water in the concrete repository is expected to maintain a pH of >10.5 for a period of at least 10 6 y. The cement matrix of the repository will retain most of the 14 CO 3 2- initially present. Bacterial production of CO 2 and CH 4 from degradation of ion-exchange resins and bitumen may contribute to 14 C release to the biosphere. However, CH 4 contributes only to a small extent to the overall carbon loss from freshwater ecosystems. The individual doses to local and regional individuals peaked with 5x10 -3 and regional individuals peaked with 5x10 -3 and 8x10 -4 μSv y -1 respectively at about 2.4x10 4 years. A total leakage of 8.4 GBq of 14 C from the repository will cause a total collective dose commitment of 1.1 manSv or 130 manSv TBq -1 . (authors)

  5. Decision-making in crisis situation at the Cea Saclay by the real-time cartography of radiological consequences

    International Nuclear Information System (INIS)

    Comte, N.; Bourgeois, L.

    2001-01-01

    The S.P.R of Saclay has developed a computer system based around three modules: term sources calculation, transfers and radiological consequences in the installation based on a compartment model for the first one; dispersion and impact on environment based on a model with Doury type Gaussian fits with dose coefficients coming from the European directive 96/29, from the ICRP 71 and Kocher for the second one; cartography with the help of a geographical information system including road map background, a Saclay center plan with environment monitoring stations and the measurements points P.P.I. ( first intervention plan) on which are superposed the panache diffusion cone and the isodoses curves. (N.C.)

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

    International Nuclear Information System (INIS)

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

    1993-02-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-02-01

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

  8. Guidelines for Remediation Strategies to Reduce the Radiological Consequences of Environmental Contamination

    Energy Technology Data Exchange (ETDEWEB)

    Fesenko, S; Howard, B J [eds.

    2012-11-15

    lessons have been learned from experience in the implementation of remediation strategies in different affected areas, most notably in countries affected by the Chernobyl accident. Both international and national guidance publications have been produced based on this experience. The former include new International Commission on Radiological Protection recommendations, the IAEA Chernobyl Forum Report and IAEA Radiological Assessment Series reports on nuclear test sites, such as the Marshall Islands; Maralinga, Australia; Mururoa and Fangataufa, French Polynesia; and Novaya Zemlya, Russian Federation. Given the considerable increase in knowledge and available information, the IAEA initiated the development of a new publication, which incorporated the additional information, lessons learned and subsequent changes in the regulatory framework. The book specifically collates, and summarizes recent activities relevant to remediation conducted under the auspices of the IAEA, but also refers to relevant studies conducted elsewhere. The text, thus, capitalizes on the knowledge and expertise gained by the many experts involved. In common with previous IAEA publications on remediation, much of the book is relevant for many other situations which may need to be remediated. Activities related to production of the publication were initiated within the IAEA environment programme and were then further developed with support from the FAO through the Joint FAO/IAEA Division of Nuclear Techniques in Food and Agriculture.

  9. Guidelines for Remediation Strategies to Reduce the Radiological Consequences of Environmental Contamination

    International Nuclear Information System (INIS)

    Fesenko, S.; Howard, B.J.

    2012-01-01

    lessons have been learned from experience in the implementation of remediation strategies in different affected areas, most notably in countries affected by the Chernobyl accident. Both international and national guidance publications have been produced based on this experience. The former include new International Commission on Radiological Protection recommendations, the IAEA Chernobyl Forum Report and IAEA Radiological Assessment Series reports on nuclear test sites, such as the Marshall Islands; Maralinga, Australia; Mururoa and Fangataufa, French Polynesia; and Novaya Zemlya, Russian Federation. Given the considerable increase in knowledge and available information, the IAEA initiated the development of a new publication, which incorporated the additional information, lessons learned and subsequent changes in the regulatory framework. The book specifically collates, and summarizes recent activities relevant to remediation conducted under the auspices of the IAEA, but also refers to relevant studies conducted elsewhere. The text, thus, capitalizes on the knowledge and expertise gained by the many experts involved. In common with previous IAEA publications on remediation, much of the book is relevant for many other situations which may need to be remediated. Activities related to production of the publication were initiated within the IAEA environment programme and were then further developed with support from the FAO through the Joint FAO/IAEA Division of Nuclear Techniques in Food and Agriculture.

  10. Radiological consequences of a bounding event sequence of Advanced Fusion Neutron Source (A-FNS)

    Energy Technology Data Exchange (ETDEWEB)

    Nakamura, Makoto M., E-mail: nakamura.makoto@qst.go.jp; Ochiai, Kentaro

    2017-05-15

    Advanced Fusion Neutron Source (A-FNS) is an accelerator-based neutron source utilizing Li(d,xn) nuclear stripping reactions to simulate D-T fusion neutrons for testing and qualifying structural and functional materials of fusion reactor components, which is to be constructed at the Rokkasho site of National Institutes for Quantum and Radiological Science and Technology, Japan, in the near future. The purpose of the study reported here is to demonstrate the ultimate safety margins of A-FNS in the worst case of release of radioactive materials outside the A-FNS confinement system. For this purpose, we analyzed a ‘bounding event’ postulated in A-FNS. The postulated event sequence consists of fire of the purification system of the liquid Li loop during the maintenance, of mobilization of the tritium and {sup 7}Be, which are the impurities of the loop, and of the entire loss of confinement of the radioactive materials. We have calculated the early doses to the public due to the release of the tritium and {sup 7}Be source terms to the environment. The UFOTRI/COSYMA simulations have been performed considering the site boundary of 500 m away from the facility. The obtained results indicate that the early dose is below the level that requires the emergent public evacuation. Such results demonstrate that the A-FNS complies with the defined safety objective against its radiation hazard. The simulation results suggest that the inherent, ultimate safety characteristic found by this study may assist a licensing process for installation of A-FNS.

  11. Proceedings of the first international conference 'The radiological consequences of the Chernobyl accident'

    Energy Technology Data Exchange (ETDEWEB)

    Karaoglou, A; Desmet, G; Kelly, G N; Menzel, H G [European Commission, Brussels (Belgium)

    1996-07-01

    Five main objectives were assigned to the EC/CIS scientific collaborative programme: improvement of the knowledge of the relationship between doses and radiation-induced health effects; updating of the arrangements for off-site emergency management response (shot- and medium term)in the even of a future nuclear accident; assisting the relevant CIS Ministries alleviate the consequences of the Chernobyl accident, in particular in the field of restoration of contaminated territories; elaboration of a scientific basis to definite the content of Community assistance programmes; updating of the local technical infrastructure, and implementation of a large programme of exchange of scientists between both Communities. The topics addressed during the Conference mainly reflect the content of the joint collaborative programme: environmental transfer and decontamination, risk assessment and management, health related issues including dosimetry. The main aims of the Conference are to present the major achievements of the joint EC/CIS collaborative research programme (1992-1995) of the consequences of the Chernobyl accident, and to promote an objective evaluation of them by the international scientific community. The Conference is taking place close to the 10{sup th} anniversary of the accident and we hope it will contribute to more objective communication of the health and environmental consequences of the Chernobyl accident, and how these may be mitigated in future. The Conference is expected to be an important milestone in the series of meetings which will take place internationally around the 10{sup th} anniversary of the nuclear accident. It also provides a major opportunity for all participants to become acquainted with software developed within the framework of the collaborative programme, namely: Geographical Information Systems displaying contamination levels and dose-commitments; Decision Support Systems for the management of contaminated territories; Decision Support

  12. Proceedings of the first international conference 'The radiological consequences of the Chernobyl accident'

    International Nuclear Information System (INIS)

    Karaoglou, A.; Desmet, G.; Kelly, G.N.; Menzel, H.G.

    1996-01-01

    Five main objectives were assigned to the EC/CIS scientific collaborative programme: improvement of the knowledge of the relationship between doses and radiation-induced health effects; updating of the arrangements for off-site emergency management response (shot- and medium term)in the even of a future nuclear accident; assisting the relevant CIS Ministries alleviate the consequences of the Chernobyl accident, in particular in the field of restoration of contaminated territories; elaboration of a scientific basis to definite the content of Community assistance programmes; updating of the local technical infrastructure, and implementation of a large programme of exchange of scientists between both Communities. The topics addressed during the Conference mainly reflect the content of the joint collaborative programme: environmental transfer and decontamination, risk assessment and management, health related issues including dosimetry. The main aims of the Conference are to present the major achievements of the joint EC/CIS collaborative research programme (1992-1995) of the consequences of the Chernobyl accident, and to promote an objective evaluation of them by the international scientific community. The Conference is taking place close to the 10 th anniversary of the accident and we hope it will contribute to more objective communication of the health and environmental consequences of the Chernobyl accident, and how these may be mitigated in future. The Conference is expected to be an important milestone in the series of meetings which will take place internationally around the 10 th anniversary of the nuclear accident. It also provides a major opportunity for all participants to become acquainted with software developed within the framework of the collaborative programme, namely: Geographical Information Systems displaying contamination levels and dose-commitments; Decision Support Systems for the management of contaminated territories; Decision Support Systems

  13. The Chernobyl – Thirty Years After The Post – Accidental Radiological – Hygienic and Medical Consequences

    Directory of Open Access Journals (Sweden)

    G. G. Onishchenko

    2016-01-01

    Full Text Available As the result of the Chernobyl NPP accident more than 200 thousand square kilometers of the European territories were contaminated by Cs-137 in the amount of above 37 kBq/m2 (1 Ci/km2 . Belorussia, Russia and Ukraine amount up to 70% of this entire affected area. More than 600 000 people were engaged in the accidental cleanup operations, 340000 were evacuated or relocated within 1986-1991. The early stage evacuation efficacy is confirmed by the absence of acute radiation syndrome among the population and by the prevented collective dose which amounts to no less than 10 000 man/Sv. The effective measure to reduce the internal radiation dose to the population at the early accidental stage was introduction of maximum tentative permissive levels of radionuclide content in the foodstuffs.Among the identified post -accident medical consequences of the Chernobyl is the radiation syndrome found in 134 emergency cleanup workers within the first 24 hours of the accident’s development. Out of that number, 28 people died within the first four months, 19 people died before 2006. The accident’s liquidators developed radiation -induced leukemia ( the attributive risk value is 45-60% . People exposed to high radiation doses display the statistically significant 18% morbidity increase of all types of solid cancers at the doses above 150 mSv. There is the statistically significant information indicating the increased amount of thyroid cancer morbidity among those who were just children and teenagers at the time of the accident. The adverse psychological consequences are accounted for not just the fear of overexposure but also for the disturbance of the habitual lifestyle especially mindful of the forced relocation.The longterm protection measures, radionuclide decay and selfcleaning of the contaminated areas resulted in the drastic reduction of the population dose in the radioactively contaminated territories. In 2015, only in some settlements of the Briansk

  14. Analysis of papers in radiological journals in recent years: a comparison of journal of Korean radiologic society and radiology

    International Nuclear Information System (INIS)

    Kim, Jin Suh; Kim, Jae Kyun; Han, Dong Bok; Lim, Tae Hwan

    1997-01-01

    The purpose of this study was to determine current trends and the mode of future development in the field of medical radiology and to promote research among the nation's radiologists by analyzing the contents of the Journal of the Korean Radiologic Society(JKRS) and Radiology. The number of articles published in JKRS each year between 1990 and 1994 was counted. The research articles in JKRS(n=740) and in Radiology(n=1748) between 1992 and 1994 were categorized according to the objective, type, topic, materials, and radiologic techniques of their contents on the basis of predetermined criteria. Domestic Masters theses(n=126) and doctoral dissertations(n=75) accepted between 1990 and 1994, and domestic materials published in international journals (n=416) between 1986 and 1994 were also categorized using the same criteria. The greatest increase in the number of articles published in JKRS was seen during 1994. The majority of these aimed to retrospectively analyse the findings of diseases while the majority of articles published in Radiology dealt prospectively with the development and/or evaluation of diagnostic methods. More variety of topics and issues was seen in Radiology than in JKRS. The number of articles of domestic materials published in international journals increased from 1986 to 1994, while the number of articles of foreign materials published in Korea was relatively stationary : A significant number of theses and dissertations dealt, mostly prospectively, with studies of pathophysiologic and/or pharmacologic mechanisms using animal models. In order to understand both current trends and the direction and mode of future developments in the field of radiology, and to be able to actively deal with challenges at the forefront of radiologic development, it is essential to review research articles published in radiology-related journals

  15. Physical and cognitive task analysis in interventional radiology

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, S [School of Psychology, University of Liverpool, Liverpool (United Kingdom); Healey, A [Royal Liverpool University Hospital, Liverpool (United Kingdom); Evans, J [Royal Liverpool University Hospital, Liverpool (United Kingdom); Murphy, M [Royal Liverpool University Hospital, Liverpool (United Kingdom); Crawshaw, M [Department of Psychology, University of Hull, Hull (United Kingdom); Gould, D [Royal Liverpool University Hospital, Liverpool (United Kingdom)

    2006-01-15

    AIM: To identify, describe and detail the cognitive thought processes, decision-making, and physical actions involved in the preparation and successful performance of core interventional radiology procedures. MATERIALS AND METHODS: Five commonly performed core interventional radiology procedures were selected for cognitive task analysis. Several examples of each procedure being performed by consultant interventional radiologists were videoed. The videos of those procedures, and the steps required for successful outcome, were analysed by a psychologist and an interventional radiologist. Once a skeleton algorithm of the procedures was defined, further refinement was achieved using individual interview techniques with consultant interventional radiologists. Additionally a critique of each iteration of the established algorithm was sought from non-participating independent consultant interventional radiologists. RESULTS: Detailed task descriptions and decision protocols were developed for five interventional radiology procedures (arterial puncture, nephrostomy, venous access, biopsy-using both ultrasound and computed tomography, and percutaneous transhepatic cholangiogram). Identical tasks performed within these procedures were identified and standardized within the protocols. CONCLUSIONS: Complex procedures were broken down and their constituent processes identified. This might be suitable for use as a training protocol to provide a universally acceptable safe practice at the most fundamental level. It is envisaged that data collected in this way can be used as an educational resource for trainees and could provide the basis for a training curriculum in interventional radiology. It will direct trainees towards safe practice of the highest standard. It will also provide performance objectives of a simulator model.

  16. Physical and cognitive task analysis in interventional radiology

    International Nuclear Information System (INIS)

    Johnson, S.; Healey, A.; Evans, J.; Murphy, M.; Crawshaw, M.; Gould, D.

    2006-01-01

    AIM: To identify, describe and detail the cognitive thought processes, decision-making, and physical actions involved in the preparation and successful performance of core interventional radiology procedures. MATERIALS AND METHODS: Five commonly performed core interventional radiology procedures were selected for cognitive task analysis. Several examples of each procedure being performed by consultant interventional radiologists were videoed. The videos of those procedures, and the steps required for successful outcome, were analysed by a psychologist and an interventional radiologist. Once a skeleton algorithm of the procedures was defined, further refinement was achieved using individual interview techniques with consultant interventional radiologists. Additionally a critique of each iteration of the established algorithm was sought from non-participating independent consultant interventional radiologists. RESULTS: Detailed task descriptions and decision protocols were developed for five interventional radiology procedures (arterial puncture, nephrostomy, venous access, biopsy-using both ultrasound and computed tomography, and percutaneous transhepatic cholangiogram). Identical tasks performed within these procedures were identified and standardized within the protocols. CONCLUSIONS: Complex procedures were broken down and their constituent processes identified. This might be suitable for use as a training protocol to provide a universally acceptable safe practice at the most fundamental level. It is envisaged that data collected in this way can be used as an educational resource for trainees and could provide the basis for a training curriculum in interventional radiology. It will direct trainees towards safe practice of the highest standard. It will also provide performance objectives of a simulator model

  17. 100 classic papers of interventional radiology: A citation analysis

    Science.gov (United States)

    Crockett, Matthew T; Browne, Ronan FJ; MacMahon, Peter J; Lawler, Leo

    2015-01-01

    AIM: To define the 100 citation classic papers of interventional radiology. METHODS: Using the database of Journal Citation Reports the 40 highest impact factor radiology journals were chosen. From these journals the 100 most cited interventional radiology papers were chosen and analysed. RESULTS: The top paper received 2497 citations and the 100th paper 200 citations. The average number of citations was 320. Dates of publication ranged from 1953 - 2005. Most papers originated in the United States (n = 67) followed by Italy (n = 20) and France (n = 10). Harvard University (n = 18) and Osped Civile (n = 11) were the most prolific institutions. Ten journals produced all of the top 100 papers with “Radiology” and “AJR” making up the majority. SN Goldberg and T Livraghi were the most prolific authors. Nearly two thirds of the papers (n = 61) were published after 1990. CONCLUSION: This analysis identifies many of the landmark interventional radiology papers and provides a fascinating insight into the changing discourse within the field. It also identifies topics, authors and institutions which have impacted greatly on the specialty. PMID:25918585

  18. The radiological consequences in the USSR from the Chernobyl accident: Description of the scheme of implementation

    International Nuclear Information System (INIS)

    Dreicer, Mona

    2004-01-01

    After October 1989 the Government of the USSR requested the IAEA to organize an international assessment of the 'concept which the USSR has evolved to enable the population to live safely in areas affected by radioactive contamination following the Chernobyl accident, and an evaluation of the effectiveness of the steps taken in these areas to safeguard the health of the population'. The IAEA responded positively to this request for special assistance. The IAEA is carried out an extensive international project involving over 100 experts who assessed the human health and environmental consequences in the affected areas of Byelorussia, the Ukraine, and the Russian Federation, and evaluate measures taken by Soviet authorities to protect the population and the environment

  19. The international Chernobyl project: Assessment of radiological consequences and evaluation of protective measures

    International Nuclear Information System (INIS)

    1991-08-01

    This brochure gives a brief account of the findings of the International Chernobyl Project. Further details will be found in the report ''The International Chernobyl Project: An Overview'' (INI22:066284/5) and in the Technical Report (INI23:011339). Measurements and assessments carried out under the project provided general corroboration of the levels of surface cesium-137 contamination reported in the official maps. The project also concluded that the official procedures for estimating radiation doses to the population were scientifically sound, although they generally resulted in overestimates of two- to threefold. The project could find no marked increase in the incidence of leukemia or cancer, but reported absorbed thyroid doses in children might lead to a statistically detectable rise in the incidence of thyroid tumors. Significant non-radiation-related health disorders were found, and the accident had substantial psychological consequences in terms of anxiety and stress

  20. Radiological Safety Analysis Computer (RSAC) Program Version 7.0 Users’ Manual

    Energy Technology Data Exchange (ETDEWEB)

    Dr. Bradley J Schrader

    2009-03-01

    The Radiological Safety Analysis Computer (RSAC) Program Version 7.0 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users’ manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods.

  1. Radiological Safety Analysis Computer (RSAC) Program Version 7.2 Users’ Manual

    Energy Technology Data Exchange (ETDEWEB)

    Dr. Bradley J Schrader

    2010-10-01

    The Radiological Safety Analysis Computer (RSAC) Program Version 7.2 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users’ manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods.

  2. Radiological Safety Analysis Computer (RSAC) Program Version 7.0 Users Manual

    International Nuclear Information System (INIS)

    Schrader, Bradley J.

    2009-01-01

    The Radiological Safety Analysis Computer (RSAC) Program Version 7.0 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods

  3. Research activity about the radiological consequences of the Chernobyl NPS accident and social activity to assist its sufferers

    International Nuclear Information System (INIS)

    Imanaka, Tetsuji; Koide, Hiroaki; Kobayashi, Keiji

    1998-01-01

    Due to the Chernobyl Accident in April 1986, a series of serious radiological consequences were brought in Ukraine, Belarus and Russia. The former Soviet Union and the authorities in the world such as IAEA, however, have been denying serious health consequences among the people around Chernobyl since the beginning of the accident. On the other hand, a lot of works indicating serious health effects of the accident have been reported by scientists in these affected countries although they are not well known in the western countries. Since 1993, under the research grant of the Toyota foundation, we have continued a cooperative program to investigate research activities in these countries about the Chernobyl accident and to look into data and information that were not known so far. The information concerning the social system and activity to assist the sufferers from the accident has been also overviewed, including legal aspects of the Chernobyl problem. Here we are presenting an outline of our cooperation activity and our work concerning dose estimation for the inhabitants around the Chernobyl NPS at the first stage after the accident. The results of our estimation suggest that at least several hundreds of inhabitants received radiation dose exceeding 1 Sv before their evacuation. The whole reports of our cooperation program will be published in English and in Japanese in the next year. (author)

  4. RadMAP: The Radiological Multi-sensor Analysis Platform

    International Nuclear Information System (INIS)

    Bandstra, Mark S.; Aucott, Timothy J.; Brubaker, Erik; Chivers, Daniel H.; Cooper, Reynold J.; Curtis, Joseph C.; Davis, John R.; Joshi, Tenzing H.; Kua, John; Meyer, Ross; Negut, Victor; Quinlan, Michael; Quiter, Brian J.; Srinivasan, Shreyas; Zakhor, Avideh; Zhang, Richard; Vetter, Kai

    2016-01-01

    The variability of gamma-ray and neutron background during the operation of a mobile detector system greatly limits the ability of the system to detect weak radiological and nuclear threats. The natural radiation background measured by a mobile detector system is the result of many factors, including the radioactivity of nearby materials, the geometric configuration of those materials and the system, the presence of absorbing materials, and atmospheric conditions. Background variations tend to be highly non-Poissonian, making it difficult to set robust detection thresholds using knowledge of the mean background rate alone. The Radiological Multi-sensor Analysis Platform (RadMAP) system is designed to allow the systematic study of natural radiological background variations and to serve as a development platform for emerging concepts in mobile radiation detection and imaging. To do this, RadMAP has been used to acquire extensive, systematic background measurements and correlated contextual data that can be used to test algorithms and detector modalities at low false alarm rates. By combining gamma-ray and neutron detector systems with data from contextual sensors, the system enables the fusion of data from multiple sensors into novel data products. The data are curated in a common format that allows for rapid querying across all sensors, creating detailed multi-sensor datasets that are used to study correlations between radiological and contextual data, and develop and test novel techniques in mobile detection and imaging. In this paper we will describe the instruments that comprise the RadMAP system, the effort to curate and provide access to multi-sensor data, and some initial results on the fusion of contextual and radiological data.

  5. RadMAP: The Radiological Multi-sensor Analysis Platform

    Energy Technology Data Exchange (ETDEWEB)

    Bandstra, Mark S., E-mail: msbandstra@lbl.gov [Nuclear Science Division, Lawrence Berkeley National Laboratory, Berkeley, CA (United States); Aucott, Timothy J. [Department of Nuclear Engineering, University of California Berkeley, CA (United States); Brubaker, Erik [Sandia National Laboratory, Livermore, CA (United States); Chivers, Daniel H.; Cooper, Reynold J. [Nuclear Science Division, Lawrence Berkeley National Laboratory, Berkeley, CA (United States); Curtis, Joseph C. [Nuclear Science Division, Lawrence Berkeley National Laboratory, Berkeley, CA (United States); Department of Nuclear Engineering, University of California Berkeley, CA (United States); Davis, John R. [Department of Nuclear Engineering, University of California Berkeley, CA (United States); Joshi, Tenzing H.; Kua, John; Meyer, Ross; Negut, Victor; Quinlan, Michael; Quiter, Brian J. [Nuclear Science Division, Lawrence Berkeley National Laboratory, Berkeley, CA (United States); Srinivasan, Shreyas [Department of Nuclear Engineering, University of California Berkeley, CA (United States); Department of Electrical Engineering and Computer Science, University of California Berkeley, CA (United States); Zakhor, Avideh; Zhang, Richard [Department of Electrical Engineering and Computer Science, University of California Berkeley, CA (United States); Vetter, Kai [Nuclear Science Division, Lawrence Berkeley National Laboratory, Berkeley, CA (United States); Department of Nuclear Engineering, University of California Berkeley, CA (United States)

    2016-12-21

    The variability of gamma-ray and neutron background during the operation of a mobile detector system greatly limits the ability of the system to detect weak radiological and nuclear threats. The natural radiation background measured by a mobile detector system is the result of many factors, including the radioactivity of nearby materials, the geometric configuration of those materials and the system, the presence of absorbing materials, and atmospheric conditions. Background variations tend to be highly non-Poissonian, making it difficult to set robust detection thresholds using knowledge of the mean background rate alone. The Radiological Multi-sensor Analysis Platform (RadMAP) system is designed to allow the systematic study of natural radiological background variations and to serve as a development platform for emerging concepts in mobile radiation detection and imaging. To do this, RadMAP has been used to acquire extensive, systematic background measurements and correlated contextual data that can be used to test algorithms and detector modalities at low false alarm rates. By combining gamma-ray and neutron detector systems with data from contextual sensors, the system enables the fusion of data from multiple sensors into novel data products. The data are curated in a common format that allows for rapid querying across all sensors, creating detailed multi-sensor datasets that are used to study correlations between radiological and contextual data, and develop and test novel techniques in mobile detection and imaging. In this paper we will describe the instruments that comprise the RadMAP system, the effort to curate and provide access to multi-sensor data, and some initial results on the fusion of contextual and radiological data.

  6. Radiological emergency response for community agencies with cognitive task analysis, risk analysis, and decision support framework.

    Science.gov (United States)

    Meyer, Travis S; Muething, Joseph Z; Lima, Gustavo Amoras Souza; Torres, Breno Raemy Rangel; del Rosario, Trystyn Keia; Gomes, José Orlando; Lambert, James H

    2012-01-01

    Radiological nuclear emergency responders must be able to coordinate evacuation and relief efforts following the release of radioactive material into populated areas. In order to respond quickly and effectively to a nuclear emergency, high-level coordination is needed between a number of large, independent organizations, including police, military, hazmat, and transportation authorities. Given the complexity, scale, time-pressure, and potential negative consequences inherent in radiological emergency responses, tracking and communicating information that will assist decision makers during a crisis is crucial. The emergency response team at the Angra dos Reis nuclear power facility, located outside of Rio de Janeiro, Brazil, presently conducts emergency response simulations once every two years to prepare organizational leaders for real-life emergency situations. However, current exercises are conducted without the aid of electronic or software tools, resulting in possible cognitive overload and delays in decision-making. This paper describes the development of a decision support system employing systems methodologies, including cognitive task analysis and human-machine interface design. The decision support system can aid the coordination team by automating cognitive functions and improving information sharing. A prototype of the design will be evaluated by plant officials in Brazil and incorporated to a future trial run of a response simulation.

  7. Decontamination analysis of a radiologically contaminated site

    International Nuclear Information System (INIS)

    Tawil, J.J.; Strenge, D.L.

    1984-01-01

    This paper presents a post-exercise analysis of decontamination options for the NUWAX-83 exercise site. Held in May 1983, the purpose of NUWAX-83 was to evaluate the ability of federal, state and local officials to respond to an accident involving nuclear weapons. A computer program, called DECON, was developed by Pacific Northwest Laboratory and used to conduct the decontamination analysis in November 1983. DECON was designed to assist personnel engaged in the planning of decontamination activities. The many features of DECON that are demonstrated in this paper contribute to its potential usefulness as a planning tool for site restoration. Strategies that are analyzed with DECON include: 1) using a Quick-Vac option, under which exterior surfaces are vacuumed before it rains; 2) protecting surfaces against precipitation; 3) prohibiting specific operations on selected surfaces; 4) requiring that specific methods be used on selected surfaces; 5) evaluating the trade-off between cleanup standards and decontamination costs; and 6) varying clean-up standards according to expected human exposure to the surface

  8. Radiological consequences of radionuclide releases to sewage systems from hospitals in Sweden

    Energy Technology Data Exchange (ETDEWEB)

    Avila, Rodolfo; Cruz, Idalmis de la [Facilia AB (Sweden); Bergman, Synnoeve [Vattenfall Power Consultants AB (Sweden); Hasselblad, Serena [Callido AB (Sweden)

    2007-08-15

    The report addresses radioactive discharges to sewers originating from hospitals, mainly in the form of the excretion of patients treated with radioisotopes for diagnostic or therapeutic purposes. Assessments of doses to the public, including sewage workers, arising from such discharges are performed. Doses are compared against the exemption level of 10 {mu}Sv/a and the dose constraint of 100 {mu}Sv/a. As a basis for the dose assessments, information on the use of radionuclides in Swedish hospitals during the period 1999-2004 is presented and estimates of discharges to the sewage systems are derived. Current sewage treatment practices in Sweden are summarised focusing particularly on the fate of sewage sludge, both in the sewage plant and outside. Radiological impact assessments are performed in two steps. The assessments in the first stage are performed using a simple screening model, not intending to predict exposures realistically but only to identify exposure pathways and radionuclides that are potentially relevant and require further consideration in the more detailed assessments. Results show that only a few of those radionuclides used in the period 1999-2004 in Swedish hospitals for radiotherapy and radiodiagnostics could lead to potentially significant doses (P-32, Y-90, Tc-99m, In-111, I-123, I-131 and Tl-201). Relevant exposure pathways are the external exposure of sewage workers (for Tc- 99m, I-123, I-131, In-111 and Tl-201) and the exposure of the public via ingestion of water (I-131) and fish (P-32, Y-90 and In-111 and I-131). The objective of the second stage is to perform realistic assessments of the doses to sewage workers and to the public through the use of contaminated agricultural sludge and through the contamination of drinking water. For this purpose, the LUCIA model was developed. This model dynamically addresses the behaviour of radionuclides in the different process steps of a sewage plant. The model can address continuous releases as well

  9. A Comprehensive Analysis of Authorship in Radiology Journals.

    Science.gov (United States)

    Dang, Wilfred; McInnes, Matthew D F; Kielar, Ania Z; Hong, Jiho

    2015-01-01

    The purpose of our study was to investigate authorship trends in radiology journals, and whether International Committee of Medical Journal Editors (ICMJE) recommendations have had an impact on these trends. A secondary objective was to explore other variables associated with authorship trends. A retrospective, bibliometric analysis of 49 clinical radiology journals published from 1946-2013 was conducted. The following data was exported from MEDLINE (1946 to May 2014) for each article: authors' full name, year of publication, primary author institution information, language of publication and publication type. Microsoft Excel Visual Basics for Applications scripts were programmed to categorize extracted data. Statistical analysis was performed to determine the overall mean number of authors per article over time, impact of ICMJE guidelines, authorship frequency per journal, country of origin, article type and language of publication. 216,271 articles from 1946-2013 were included. A univariate analysis of the mean authorship frequency per year of all articles yielded a linear relationship between time and authorship frequency. The mean number of authors per article in 1946 (1.42) was found to have increased consistently by 0.07 authors/ article per year (R² = 0.9728, Pjournals, country of origin, language of publication and article type. Overall authorship for 49 radiology journals across 68 years has increased markedly with no demonstrated impact from ICMJE guidelines. A higher number of authors per article was seen in articles from: higher impact journals, European and Asian countries, original research type, and those journals who explicitly endorse the ICMJE guidelines.

  10. Source term and radiological consequence evaluation for nuclear accidents using a 'hand type' methodology

    International Nuclear Information System (INIS)

    Margeanu, Sorin; Tatiana, Angelescu

    2005-01-01

    In the last decades, hand type calculations have been replaced by computerized solutions, which are much more accurate, but the preparation of an input to run the code can be a time consuming process and can require a laborious work. This is why, a place for hand calculation based on nomograms still exist in some areas. An example is emergency response to an accidental release of radioactive contaminants when the health of persons close to the accident site might be at risk. In this case, results from computerized accident consequences assessment models may be delayed due to the equipment malfunction or the time required developing minimal input files and performing the calculations (typically more than five minutes). A simple nomogram (developed using computerized dispersion model calculations) can provide dispersion and dose estimates within a minute. The paper presents the methodology used for these 'hand type' calculation and the nomograms, figures and tables used to evaluate the dose to an individual close to the release point. In order to illustrate the use of methodology, a hypothetical severe accident scenario involving 14-MW INR-TRIGA research reactor was considered. (authors)

  11. Pathway analysis concepts for radiological impact assessment

    International Nuclear Information System (INIS)

    Moroney, J.R.

    1992-06-01

    The concepts underlying exposure pathways analysis are outlined with reference to the features of the two broad types of radionuclide transport models now in use - dynamic and steady-state - and the methods for constructing and developing them. By way of illustration, representative radiation doses are estimated for the four main exposure pathways likely to be involved in the land application of effluent water from Retention Pond 2 of Ranger Uranium Mines. These include: external irradiation by 226 Ra and natural uranium (Un at) in soil, ingestion of 226 Ra and Un at in food, inhalation of 222 Rn daughter products from 226 Rn in soil, and inhalation of 226 Ra and Un at in airborne dust resuspended from soil. Consideration has been given to local residents pursuing a traditional lifestyle on conclusion of the land application program. Because of the possible importance of the contribution from resuspended dust, currently available data are explored in refining the methodology for the pathway and developing a more appropriate model for it. 37 refs., 9 tabs., 6 figs

  12. Cost benefit analysis in diagnostic radiology: glossary and definitions

    International Nuclear Information System (INIS)

    Golder, W.

    1999-01-01

    Cost efficiency analyses in clinical radiology require the application of methods and techniques that are not yet part of the academic qualifications of the specialists. The procedures used are borrowed from economics, decision theory, applied social sciences, epidemiology and statistics. Many expressions hail from the angloamerican literature and are presently not yet germanized unequivocally. This survey is intended to present main terms of cost efficiency analysis in the English version as well as a German translation, to give a clear definition and, if necessary, explanatory notes, and to illustrate their application by means of concrete radiologic examples. The selection of the terms is based on the hierarchical models of health technology assessment resp. clinical outcome research by Fryback and Thronbury resp. Maisey and Hutton. In concrete terms, both the differences between benefit, outcomes, and utility and the differences between effectiveness, efficacy and efficiency and the differences between direct, indirect, intangible, and marginal costs are explained. True cost efficiency analysis is compared with cost effectiveness analysis, cost identification analysis, cost minimization analysis, and cost utility analysis. Applied social sciences are represented by the Medical Outcomes Study Short Form-36 and the QALY conception. From decision theory both the analysis of hypothetical alternatives and the Markov model are taken. Finally, sensitivity analysis and the procedures of combined statistical evaluation of comparable results (meta-analysis) are quoted. (orig.) [de

  13. The Role of Countermeasures in Mitigating the Radiological Consequences of Nuclear Power Plant Accidents

    Energy Technology Data Exchange (ETDEWEB)

    Tawfik, F. S.; Abdel-Aal, M.M., E-mail: basant572000@yahoo.com [Siting & Environmental Department, Nuclear and Radiological Regulatory Authority, Cairo (Egypt)

    2014-10-15

    During the Fukushima accident the mitigation actions played an important role to decrease the consequences of the accident. The countermeasures are the actions that should be taken after the occurrence of a nuclear accident to protect the public against the associated risk. The actions may be represented by sheltering, evacuation, distribution of stable iodine tablets and/or relocation. This study represents a comprehensive probabilistic study to investigate the role of the adoption of the countermeasures in case of a hypothetical accident of type LOCA for a nuclear power plant of PWR (1000 Mw) type. This work was achieved through running of the PC COSYMA{sup (1)} code. The effective doses in different organs, short and long term health effects, and the associated risks were calculated with and without countermeasures. In addition, the overall costs of the accident and the costs of countermeasures are estimated which represent our first trials to know how much the postulated accident costs. The source term of a hypothetical accident is determined by knowing the activity of the core inventory. The meteorological conditions around the site in addition to the population distribution were utilized as input parameters. The stability conditions and the height of atmospheric boundary layers ABL of the concerned site were determined by developing a computer program utilizing Pasquill-Gifford atmospheric stability conditions. The results showed that, the area around the site requires early and late countermeasures actions after the accident especially in the downwind sectors. For late countermeasures, the duration of relocation ranged from about two to 10 years. The adoption of the countermeasures increases the costs of emergency planning by 40% but reduces the risk associated with the accident. (author)

  14. Radiological consequences of atmospheric releases from coal-fired power plants

    International Nuclear Information System (INIS)

    Tveten, U.

    1985-06-01

    The report deals with the individual and collective doses resulting from radioactive materials contained in the stack releases of coal-fired power plants. A critical analysis of relevant calculations in literature is given. The different reports analyzed show a very wide range in calculated doses. To a great extent these differences may be explained by the wide range in the assumptions adopted. There is also disagreement on what exposure pathways are the most important, and what nuclides contribute most to calculated doses. A most probable value of 0.5 mrem/year for the maximum individual effective dose equivalent commitment, is indicated in the report

  15. Uncertainties in geologic disposal of high-level wastes - groundwater transport of radionuclides and radiological consequences

    International Nuclear Information System (INIS)

    Kocher, D.C.; Sjoreen, A.L.; Bard, C.S.

    1983-01-01

    The analysis for radionuclide transport in groundwater considers models and methods for characterizing (1) the present geologic environment and its future evolution due to natural geologic processes and to repository development and waste emplacement, (2) groundwater hydrology, (3) radionuclide geochemistry, and (4) the interactions among these phenomena. The discussion of groundwater transport focuses on the nature of the sources of uncertainty rather than on quantitative estimates of their magnitude, because of the lack of evidence that current models can provide realistic quantitative predictions of radionuclide transport in groundwater for expected repository environments. The analysis for the long-term health risk to man following releases of long-lived radionuclides to the biosphere is more quantitative and involves estimates of uncertainties in (1) radionuclide concentrations in man's exposure environment, (2) radionuclide intake by exposed individuals per unit concentration in the environment, (3) the dose per unit intake, (4) the number of exposed individuals, and (5) the health risk per unit dose. For the important long-lived radionuclides in high-level waste, uncertainties in most of the different components of a calculation of individual and collective dose per unit release appear to be no more than two or three orders of magnitude; these uncertainties are certainly much less than uncertainties in predicting groundwater transport of radionuclides between a repository and the biosphere. Several limitations in current models for predicting the health risk to man per unit release to the biosphere are discussed

  16. Radiological consequences of a hypothetical ''roof breakdown'' accident of the Chernobyl sarcophagus

    International Nuclear Information System (INIS)

    Pretzsch, G.

    1997-01-01

    On behalf of the German Federal Ministry for Environment, Nature Conservation and Nuclear Safety GRS performed investigations with the aim to improve the safety of the Chernobyl Unit 4 shelter in close connection with the Ministry for Environment and Nuclear Safety of the Ukraina from 1992 to 1995. One of the tasks of the working programme was concerned with the analysis of hypothetical accidents of the present shelter, which comprises the newly built Sarcophagus and the remaining ruins of Unit 4. In close collaboration with Ukrainian and Russian experts the maximum hypothetical accident was defined to be the breakdown of the roof of the Sarcophagus and subsequent release of the radioactive dust which is mainly located in the destroyed reactor hall and the neighboring rooms

  17. Regression analysis of radiological parameters in nuclear power plants

    International Nuclear Information System (INIS)

    Bhargava, Pradeep; Verma, R.K.; Joshi, M.L.

    2003-01-01

    Indian Pressurized Heavy Water Reactors (PHWRs) have now attained maturity in their operations. Indian PHWR operation started in the year 1972. At present there are 12 operating PHWRs collectively producing nearly 2400 MWe. Sufficient radiological data are available for analysis to draw inferences which may be utilised for better understanding of radiological parameters influencing the collective internal dose. Tritium is the main contributor to the occupational internal dose originating in PHWRs. An attempt has been made to establish the relationship between radiological parameters, which may be useful to draw inferences about the internal dose. Regression analysis have been done to find out the relationship, if it exist, among the following variables: A. Specific tritium activity of heavy water (Moderator and PHT) and tritium concentration in air at various work locations. B. Internal collective occupational dose and tritium release to environment through air route. C. Specific tritium activity of heavy water (Moderator and PHT) and collective internal occupational dose. For this purpose multivariate regression analysis has been carried out. D. Tritium concentration in air at various work location and tritium release to environment through air route. For this purpose multivariate regression analysis has been carried out. This analysis reveals that collective internal dose has got very good correlation with the tritium activity release to the environment through air route. Whereas no correlation has been found between specific tritium activity in the heavy water systems and collective internal occupational dose. The good correlation has been found in case D and F test reveals that it is not by chance. (author)

  18. Analysis of the consequences of 'thermite' reaction

    International Nuclear Information System (INIS)

    Yorio, Daniel; Cincotta, Daniel O.; Camacho, Esteban F.; Bruno, Hernan R.; Boero, Norma L.

    1999-01-01

    The mixture of Al-U 3 O 8 is not in a state of chemical equilibrium, and at temperatures of between 850 degree C and 1000 degree C, it reacts exo thermally. This is known, in corresponding bibliography, as a 'Thermite reaction'. This mixture is used in the manufacturing of the plate-type fuel used in research reactors. It has been pointed out that the release of energy caused by this type of reactions might represent a risk in case of accidents in this type of reactor. Conclusions, in general, tend to indicate that no such risk exists, although no concrete assurance is given that this is the case, and this fact, therefore, leaves room for doubt. The objective of this paper is to provide an in-depth study of what happens to a fuel plate when it is subjected to thermite reaction. We will, furthermore, analyze the consequences of the release of energy generated by this type of reaction within the core of the reactor, clearly defining the problem for this type of fuel and this kind of reactor

  19. Radiological consequences of zinc-rich filter cake at Hoogovens Steel industry in IJmuiden, Netherlands (a modelled study)

    International Nuclear Information System (INIS)

    Laheij, G.M.H.; Eggink, G.J.

    1996-08-01

    In accordance with the revised Euratom 'basic safety standards', the Member States have to fill in the details of their own radiation protection policy on radionuclides from natural sources. In this framework the radiological consequences of zinc-rich filter cake at a storage facility of the steelplant Hoogovens Staal, in IJmuiden, Netherlands, were investigated in a model study. Also investigated were the consequences of possible transport of the filter cake to a storage facility in the country. The radiation dose was calculated for Hoogovens workers and for members of the population. For workers, the relevant exposure pathways are inhalation of resuspended filter cake, direct ingestion of filter cake and external radiation. Relevant exposure pathways for members of the population are inhalation of resuspended filter cake, ingestion of green vegetables on which resuspended filter cake is deposited and external radiation, which for workers at the storage facility the radiation dose is 7 mSv/a. The radiation dose for drivers during transport and for workers at a C3-storage facility depends strongly on whether the material is immobilized or not. The maximum radiation dose for both the transport and storage is expected to be almost equal to the radiation dose for workers at the storage facility at Hoogovens. For members of the population living around the storage facility at Hoogovens, the radiation dose is 3.6 mSv/a. Here too, the radiation dose at the storage facility depends strongly on whether the material is immobilized or not. During transport no radiation dose above the secondary level of 0.4 mSv/a is expected due to the short exposure times. 23 refs

  20. Analysis of a quality assurance program in diagnostic radiology

    International Nuclear Information System (INIS)

    Goethlin, J.H.

    1986-01-01

    Retake analysis before and after introduction of a quality assurance program showed a 45% reduction of the retake rate. The most important changes concerning equipment and organizing of labour were: (1) More detailed inspection of development machines and X-ray generators, (2) new cassettes and intensifying screens, (3) reduction of the number of film formats used, (4) information and instruction of personnel. Cost reductions and profit from increased examination rate amounted to 4.5% of the overall operating costs of the radiologic department. (author)

  1. Apply Functional Modelling to Consequence Analysis in Supervision Systems

    DEFF Research Database (Denmark)

    Zhang, Xinxin; Lind, Morten; Gola, Giulio

    2013-01-01

    This paper will first present the purpose and goals of applying functional modelling approach to consequence analysis by adopting Multilevel Flow Modelling (MFM). MFM Models describe a complex system in multiple abstraction levels in both means-end dimension and whole-part dimension. It contains...... consequence analysis to practical or online applications in supervision systems. It will also suggest a multiagent solution as the integration architecture for developing tools to facilitate the utilization results of functional consequence analysis. Finally a prototype of the multiagent reasoning system...... causal relations between functions and goals. A rule base system can be developed to trace the causal relations and perform consequence propagations. This paper will illustrate how to use MFM for consequence reasoning by using rule base technology and describe the challenges for integrating functional...

  2. Potential Indoor Worker Exposure From Handling Area Leakage: Dose Calculation Methodology and Example Consequence Analysis

    International Nuclear Information System (INIS)

    Nes, Razvan; Benke, Roland R.

    2008-01-01

    The U.S. Department of Energy (DOE) is currently considering design options for preclosure facilities in a license application for a geologic repository for spent nuclear fuel and high-level radioactive waste at Yucca Mountain, Nevada. The Center for Nuclear Waste Regulatory Analyses (CNWRA) developed the PCSA Tool Version 3.0.0 software for the U.S. Nuclear Regulatory Commission (NRC) to aid in the regulatory review of a potential DOE license application. The objective of this paper is to demonstrate PCSA Tool modeling capabilities (i.e., a generic two-compartment, mass-balance model) for estimating radionuclide concentrations in air and radiological dose consequences to indoor workers in a control room from potential leakage of radioactively contaminated air from an adjacent handling area. The presented model computes internal and external worker doses from inhalation and submersion in a finite cloud of contaminated air in the control room and augments previous capabilities for assessing indoor worker dose. As a complement to the example event sequence frequency analysis in the companion paper, example consequence calculations are presented in this paper for the postulated event sequence. In conclusion: this paper presents a model for estimating radiological doses to indoor workers for the leakage of airborne radioactive material from handling areas. Sensitivity of model results to changes in various input parameters was investigated via illustrative example calculations. Indoor worker dose estimates were strongly dependent on the duration of worker exposure and the handling-area leakage flow rate. In contrast, doses were not very sensitive to handling-area exhaust ventilation flow rates. For the presented example, inhalation was the dominant radiological dose pathway. The two companion papers demonstrate independent analysis capabilities of the regulator for performing confirmatory calculations of frequency and consequence, which assist the assessment of worker

  3. 40 CFR 68.165 - Offsite consequence analysis.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 15 2010-07-01 2010-07-01 false Offsite consequence analysis. 68.165 Section 68.165 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) CHEMICAL ACCIDENT PREVENTION PROVISIONS Risk Management Plan § 68.165 Offsite consequence...

  4. Cost-effectiveness analysis of countermeasures using accident consequence assessment models

    International Nuclear Information System (INIS)

    Alonso, A.; Gallego, E.

    1987-01-01

    In the event of a large release of radionuclides from a nuclear power plant, protective actions for the population potentially affected must be implemented. Cost-effectiveness analysis will be useful to define the countermeasures and the criteria needed to implement them. This paper shows the application of Accident Consequence Assessment (ACA) models to cost-effectiveness analysis of emergency and long-term countermeasures, making use of the different relationships between dose, contamination levels, affected areas and population distribution, included in such a model. The procedure is illustrated with the new Melcor Accident Consequence Code System (MACCS 1.3), developed at Sandia National Laboratories (USA), for a fixed accident scenario. Different alternative actions are evaluated with regard to their radiological and economical impact, searching for an 'optimum' strategy. (author)

  5. The influence of the physico-chemical form of the aerosol on the radiological consequences of notional accidental releases of radioactivity from a fast breeder reactor

    International Nuclear Information System (INIS)

    Kelly, G.N.; Jones, J.A.; Simmonds, J.R.

    1979-01-01

    The radiological consequences of a wide range of notional accidental releases from a 1300 MW(e) LMFBR (Liquid Metal-cooled Fast Breeder Reactor) were assessed in a study published by the National Radiological Protection Board (NRPB) in 1977. In that study representative values were in general adopted for each of the important parameters while recognising that in reality they could vary considerably. The present study is concerned with the sensitivity of the predicted consequences to the physico-chemical form of the released aerosol. Of particular interest is the importance of a mixed sodium-transuranium element aerosol which may be formed in accidental releases of activity from sodium cooled FBRs. Two significant findings emerge from the study. First the predicted consequences in general are relatively insensitive to the range of physico-chemical forms analysed. For generic assessments therefore it is sufficient to assume the properties of the aerosol adopted in the initial study (1 μm AMAD and each element in the oxide form); the exception concerns the estimation of the incidence of early morbidity, and to a lesser extent early mortality, but only for a limited range of release composition. The second finding is that the radiological consequences are not, contrary to what might have been expected, significantly increased for the release of a mixed sodium-element aerosol

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

    International Nuclear Information System (INIS)

    Thome, D.J.

    2000-01-01

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

  7. Analysis of the Importance of Subjects to Improve the Educational Curriculum in the Radiological Science: Focused on Radiological Technologists

    International Nuclear Information System (INIS)

    Kim, Jung Hoon; Ko, Seong Jin; Kang, Se Sik; Kim, Dong Hyun; Kim, Chang Soo

    2012-01-01

    In this study a group of experts and clinical radiological technologists were surveyed to evaluate the clinical importance of current subjects in the radiological sciences. For the data collection and analysis, an open-ended questionnaire was distributed to the group of experts, and a multiple choice questionnaire was distributed to radiological technologists. Subjects were classified into 9 groups for analysis of the importance of subjects, and in regard to the questionnaire design for measurement of variables, departments and type of hospital were set up as independent variables, and the 9 groups of subjects were set up as dependent variables. As a result, clinical radiological technologists perceived Diagnostic Imaging Technology and practical courses, including general radiography, CT and MRI, as the most clinically necessary subjects, and the group of experts placed most weight on basic courses for the major. The result of this study suggests that the curriculum should be revised in a way that combines theory and practice in order to foster radiological technologists capable of adapting to the rapidly changing healthcare environment.

  8. Fractal-Based Image Analysis In Radiological Applications

    Science.gov (United States)

    Dellepiane, S.; Serpico, S. B.; Vernazza, G.; Viviani, R.

    1987-10-01

    We present some preliminary results of a study aimed to assess the actual effectiveness of fractal theory and to define its limitations in the area of medical image analysis for texture description, in particular, in radiological applications. A general analysis to select appropriate parameters (mask size, tolerance on fractal dimension estimation, etc.) has been performed on synthetically generated images of known fractal dimensions. Moreover, we analyzed some radiological images of human organs in which pathological areas can be observed. Input images were subdivided into blocks of 6x6 pixels; then, for each block, the fractal dimension was computed in order to create fractal images whose intensity was related to the D value, i.e., texture behaviour. Results revealed that the fractal images could point out the differences between normal and pathological tissues. By applying histogram-splitting segmentation to the fractal images, pathological areas were isolated. Two different techniques (i.e., the method developed by Pentland and the "blanket" method) were employed to obtain fractal dimension values, and the results were compared; in both cases, the appropriateness of the fractal description of the original images was verified.

  9. Northern Marshall Islands radiological survey: sampling and analysis summary

    Energy Technology Data Exchange (ETDEWEB)

    Robison, W.L.; Conrado, C.L.; Eagle, R.J.; Stuart, M.L.

    1981-07-23

    A radiological survey was conducted in the Northern Marshall Islands to document reamining external gamma exposures from nuclear tests conducted at Enewetak and Bikini Atolls. An additional program was later included to obtain terrestrial and marine samples for radiological dose assessment for current or potential atoll inhabitants. This report is the first of a series summarizing the results from the terrestrial and marine surveys. The sample collection and processing procedures and the general survey methodology are discussed; a summary of the collected samples and radionuclide analyses is presented. Over 5400 samples were collected from the 12 atolls and 2 islands and prepared for analysis including 3093 soil, 961 vegetation, 153 animal, 965 fish composite samples (average of 30 fish per sample), 101 clam, 50 lagoon water, 15 cistern water, 17 groundwater, and 85 lagoon sediment samples. A complete breakdown by sample type, atoll, and island is given here. The total number of analyses by radionuclide are 8840 for /sup 241/Am, 6569 for /sup 137/Cs, 4535 for /sup 239 +240/Pu, 4431 for /sup 90/Sr, 1146 for /sup 238/Pu, 269 for /sup 241/Pu, and 114 each for /sup 239/Pu and /sup 240/Pu. A complete breakdown by sample category, atoll or island, and radionuclide is also included.

  10. Northern Marshall Islands radiological survey: sampling and analysis summary

    International Nuclear Information System (INIS)

    Robison, W.L.; Conrado, C.L.; Eagle, R.J.; Stuart, M.L.

    1981-01-01

    A radiological survey was conducted in the Northern Marshall Islands to document reamining external gamma exposures from nuclear tests conducted at Enewetak and Bikini Atolls. An additional program was later included to obtain terrestrial and marine samples for radiological dose assessment for current or potential atoll inhabitants. This report is the first of a series summarizing the results from the terrestrial and marine surveys. The sample collection and processing procedures and the general survey methodology are discussed; a summary of the collected samples and radionuclide analyses is presented. Over 5400 samples were collected from the 12 atolls and 2 islands and prepared for analysis including 3093 soil, 961 vegetation, 153 animal, 965 fish composite samples (average of 30 fish per sample), 101 clam, 50 lagoon water, 15 cistern water, 17 groundwater, and 85 lagoon sediment samples. A complete breakdown by sample type, atoll, and island is given here. The total number of analyses by radionuclide are 8840 for 241 Am, 6569 for 137 Cs, 4535 for 239+240 Pu, 4431 for 90 Sr, 1146 for 238 Pu, 269 for 241 Pu, and 114 each for 239 Pu and 240 Pu. A complete breakdown by sample category, atoll or island, and radionuclide is also included

  11. Radionuclides in Bayer process residues: previous analysis for radiological protection

    International Nuclear Information System (INIS)

    Cuccia, Valeria; Rocha, Zildete; Oliveira, Arno H. de

    2011-01-01

    Natural occurring radionuclides are present in many natural resources. Human activities may enhance concentrations of radionuclides and/or enhance potential of exposure to naturally occurring radioactive material (NORM). The industrial residues containing radionuclides have been receiving a considerable global attention, because of the large amounts of NORM containing wastes and the potential long term risks of long-lived radionuclides. Included in this global concern, this work focuses on the characterization of radioactivity in the main residues of Bayer process for alumina production: red mud and sand samples. Usually, the residues of Bayer process are named red mud, in their totality. However, in the industry where the samples were collected, there is an additional residues separation: sand and red mud. The analytical techniques used were gamma spectrometry (HPGe detector) and neutron activation analysis. The concentrations of radionuclides are higher in the red mud than in the sand. These solid residues present activities concentrations enhanced, when compared to bauxite. Further uses for the residues as building material must be more evaluated from the radiological point of view, due to its potential of radiological exposure enhancement, specially caused by radon emission. (author)

  12. The choice of cement for the manufacture of concrete to be activated: the potential for reducing the radiological consequences of reactor decommissioning

    International Nuclear Information System (INIS)

    Woollam, P.B.

    1985-05-01

    This report presents trace element analyses of some candidate cements which might be used in the manufacture of Sizewell 'B' concrete. It completes a programme of work whose aim was to investigate the potential for reducing the radiological consequences of reactor decommissioning through selection of construction materials for activated components. In particular, consideration has been given to the potential for reducing the concentration of elements known to activate to long lived daughters. (U.K.)

  13. Manipulation of mental models of anatomy in interventional radiology and its consequences for design of human–computer interaction

    NARCIS (Netherlands)

    Varga, E.; Pattynama, P.M.T.; Freudenthal, A.

    2012-01-01

    Interventional radiology procedures require extensive cognitive processing from the physician. A set of these cognitive functions are aimed to be replaced by technology in order to reduce the cognitive load. However, limited knowledge is available regarding mental processes in interventional

  14. Cost accounting of radiological examinations. Cost analysis of radiological examinations of intermediate referral hospitals and general practice.

    Science.gov (United States)

    Lääperi, A L

    1996-01-01

    The purpose of this study was to analyse the cost structure of radiological procedures in the intermediary referral hospitals and general practice and to develop a cost accounting system for radiological examinations that takes into consideration all relevant cost factors and is suitable for management of radiology departments and regional planning of radiological resources. The material comprised 174,560 basic radiological examinations performed in 1991 at 5 intermediate referral hospitals and 13 public health centres in the Pirkanmaa Hospital District in Finland. All radiological departments in the hospitals were managed by a specialist in radiology. The radiology departments at the public health care centres operated on a self-referral basis by general practitioners. The data were extracted from examination lists, inventories and balance sheets; parts of the data were estimated or calculated. The radiological examinations were compiled according to the type of examination and equipment used: conventional, contrast medium, ultrasound, mammography and roentgen examinations with mobile equipment. The majority of the examinations (87%) comprised conventional radiography. For cost analysis the cost items were grouped into 5 cost factors: personnel, equipment, material, real estate and administration costs. The depreciation time used was 10 years for roentgen equipment, 5 years for ultrasound equipment and 5 to 10 years for other capital goods. An annual interest rate of 10% was applied. Standard average values based on a sample at 2 hospitals were used for the examination-specific radiologist time, radiographer time and material costs. Four cost accounting versions with varying allocation of the major cost items were designed. Two-way analysis of variance of the effect of different allocation methods on the costs and cost structure of the examination groups was performed. On the basis of the cost analysis a cost accounting program containing both monetary and

  15. Aspects of uncertainty analysis in accident consequence modeling

    International Nuclear Information System (INIS)

    Travis, C.C.; Hoffman, F.O.

    1981-01-01

    Mathematical models are frequently used to determine probable dose to man from an accidental release of radionuclides by a nuclear facility. With increased emphasis on the accuracy of these models, the incorporation of uncertainty analysis has become one of the most crucial and sensitive components in evaluating the significance of model predictions. In the present paper, we address three aspects of uncertainty in models used to assess the radiological impact to humans: uncertainties resulting from the natural variability in human biological parameters; the propagation of parameter variability by mathematical models; and comparison of model predictions to observational data

  16. Ireland's recent contribution to the radiological literature; a bibliometric analysis

    LENUS (Irish Health Repository)

    Redmond, CE

    2017-04-01

    The aim of this study was to identify and analyse all articles published by Irish radiology departments in the medical literature since the year 2000. The PubMed database was searched to identify and review all articles published by radiologists based in the Republic of Ireland or Northern Ireland. Citation counts were then obtained and the top ten most cited articles were identified. There were 781 articles published during the study period. Of these, 558 (71%) were published in radiology journals and the remaining 223 (29%) were published in general medical journals. Abdominal radiology was the most represented sub-specialty (33% of all articles). There was a general trend of increased publications per year. Only 75 (9.6%) of articles were collaborative efforts by more than one radiology department. Irish radiology departments have a considerable research output and this has increased since the year 2000. More collaborative research between Irish radiology departments is encouraged

  17. Consequences of Fukushima 11032011 - Radiological consequences from the nuclear accidents in Fukushima on 11 March 2011; Fukushima Auswirkung 11032011 -- Radiologische Auswirkungen aus den kerntechnischen Unfaellen in Fukushima vom 11.03.2011

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-12-15

    On 11 March 2011 at 14.46 the strongest earthquake ever recorded in Japan struck the Pacific coast in front of Fukushima. The earthquake and the following tsunami damaged the nuclear power plants in Fukushima Dai-ichi to such an extent that the Japanese government declared the state of catastrophic accident with degree 7 according to the International Nuclear and Radiological Event Scale (INES). At Fukushima Dai-ichi there were 6 boiling water reactors (BWR), a storage pool for spent fuel assemblies and a dry cask storage. 12 km apart at Fukushima Dai-ni there were 4 more BWR. At the moment of the earthquake the reactors 1 to 3 of Fukushima Dai-ichi, as well as the 4 reactors at Fukushima Dai-ni, were at full power, while the reactors 4 to 6 of Fukushima Dai-ichi were shut down for revision. From 12 March 2011 on, fairly large quantities of radioactive materials were released from Fukushima Dai-ichi reactors with meaningful consequences on the population in the near neighbourhood. The irradiation from the radioactivity bearing clouds, the ingestion and inhalation, and the deposit of radioactive materials on the ground threatened the population. The inhabitants of large areas had to be evacuated. Furthermore, radioactive materials contaminated the drinking water, the sea water and finally the plants and animals, i.e. the food chain of the people living there. The Swiss Federal Nuclear Safety Inspectorate (ENSI) continuously proceeded with the evaluation of the situation in Japan and a specialists' team made a detailed analysis of the accident, with emphasis on the human and organisational factors and on the lessons learned from this. The present report describes the present knowledge about the radiological consequences of the accident in Fukushima Dai-ichi on the population in the neighbourhood and on the staff at the power plant, until October 2011. First, the unrolling of the accident and its consequences on the plant site are analysed according to

  18. Hanford Waste Tank Bump Accident and Consequence Analysis

    International Nuclear Information System (INIS)

    BRATZEL, D.R.

    2000-01-01

    This report provides a new evaluation of the Hanford tank bump accident analysis and consequences for incorporation into the Authorization Basis. The analysis scope is for the safe storage of waste in its current configuration in single-shell and double-shell tanks

  19. Analysis of operation TEAPOT nuclear test ZUCCHINI radiological and meterological data

    International Nuclear Information System (INIS)

    Quinn, V.E.

    1987-03-01

    This report describes the Weather Service Nuclear Support Office (WSNSO) analyses of the radiological and meteorological data collected for the ZUCCHINI nuclear test of Operation TEAPOT. Inconsistencies in the radiological data and their resolution are discussed. The methods of normalizing the radiological data to a standard time and estimating fallout-arrival times are presented. The meteorological situations on event day and the following day are described. A comparison of the WSNSO fallout analysis with an analysis performed in the 1950's is presented. The radiological data used to derive the WSNSO 1986 fallout pattern are tabulated in an appendix

  20. A study on the weather sampling method for probabilistic consequence analysis

    International Nuclear Information System (INIS)

    Oh, Hae Cheol

    1996-02-01

    The main task of probabilistic accident consequence analysis model is to predict the radiological situation and to provide a reliable quantitative data base for making decisions on countermeasures. The magnitude of accident consequence is depended on the characteristic of the accident and the weather coincident. In probabilistic accident consequence analysis, it is necessary to repeat the atmospheric dispersion calculation with several hundreds of weather sequences to predict the full distribution of consequences which may occur following a postulated accident release. It is desirable to select a representative sample of weather sequences from a meteorological record which is typical of the area over which the released radionuclides will disperse and which spans a sufficiently long period. The selection process is done by means of sampling techniques from a full year of hourly weather data characteristic of the plant site. In this study, the proposed Weighted importance sampling method selects proportional to the each bin size to closely approximate the true frequency distribution of weather condition at the site. The Weighted importance sampling method results in substantially less sampling uncertainty than the previous technique. The proposed technique can result in improve confidence in risk estimates

  1. Research activities about the radiological consequences of the Chernobyl NPS accident and social activities to assist the sufferers by the accident

    International Nuclear Information System (INIS)

    Imanaka, T.

    1998-03-01

    The 12th anniversary is coming soon of the accident at the Chernobyl nuclear power station in the former USSR on April 26, 1986. Many issues are, however, still unresolved about the radiological impacts on the environment and people due to the Chernobyl accident. This report contains the results of an international collaborative project about the radiological consequences of the Chernobyl accident, carried out from November 1995 to October 1997 under the research grant of the Toyota foundation. Collaborative works were promoted along with the following 5 sub-themes: 1) General description of research activities in Russia, Belarus and Ukraine concerning the radiological consequences of the accident. 2) Investigation of the current situation of epidemiological studies about Chernobyl in each affected country. 3) Investigation of acute radiation syndrome among inhabitants evacuated soon after the accident from the 30 km zone around the Chernobyl NPS. 4) Overview of social activities to assist the sufferers by the accident in each affected country. 5) Preparation of special reports of interesting studies being carried out in each affected country. The 27 papers are indexed individually. (J.P.N.)

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

    International Nuclear Information System (INIS)

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

    1985-08-01

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

  3. Economic Consequence Analysis of Disasters: The ECAT Software Tool

    Energy Technology Data Exchange (ETDEWEB)

    Rose, Adam; Prager, Fynn; Chen, Zhenhua; Chatterjee, Samrat; Wei, Dan; Heatwole, Nathaniel; Warren, Eric

    2017-04-15

    This study develops a methodology for rapidly obtaining approximate estimates of the economic consequences from numerous natural, man-made and technological threats. This software tool is intended for use by various decision makers and analysts to obtain estimates rapidly. It is programmed in Excel and Visual Basic for Applications (VBA) to facilitate its use. This tool is called E-CAT (Economic Consequence Analysis Tool) and accounts for the cumulative direct and indirect impacts (including resilience and behavioral factors that significantly affect base estimates) on the U.S. economy. E-CAT is intended to be a major step toward advancing the current state of economic consequence analysis (ECA) and also contributing to and developing interest in further research into complex but rapid turnaround approaches. The essence of the methodology involves running numerous simulations in a computable general equilibrium (CGE) model for each threat, yielding synthetic data for the estimation of a single regression equation based on the identification of key explanatory variables (threat characteristics and background conditions). This transforms the results of a complex model, which is beyond the reach of most users, into a "reduced form" model that is readily comprehensible. Functionality has been built into E-CAT so that its users can switch various consequence categories on and off in order to create customized profiles of economic consequences of numerous risk events. E-CAT incorporates uncertainty on both the input and output side in the course of the analysis.

  4. Probabilistic accident consequence uncertainty analysis -- Early health effects uncertainty assessment. Volume 2: Appendices

    Energy Technology Data Exchange (ETDEWEB)

    Haskin, F.E. [Univ. of New Mexico, Albuquerque, NM (United States); Harper, F.T. [Sandia National Labs., Albuquerque, NM (United States); Goossens, L.H.J.; Kraan, B.C.P. [Delft Univ. of Technology (Netherlands)

    1997-12-01

    The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in 1990. These codes estimate the consequence from the accidental releases of radiological material from hypothesized accidents at nuclear installations. In 1991, the US Nuclear Regulatory Commission and the Commission of the European Communities began cosponsoring a joint uncertainty analysis of the two codes. The ultimate objective of this joint effort was to systematically develop credible and traceable uncertainty distributions for the respective code input variables. A formal expert judgment elicitation and evaluation process was identified as the best technology available for developing a library of uncertainty distributions for these consequence parameters. This report focuses on the results of the study to develop distribution for variables related to the MACCS and COSYMA early health effects models. This volume contains appendices that include (1) a summary of the MACCS and COSYMA consequence codes, (2) the elicitation questionnaires and case structures, (3) the rationales and results for the panel on early health effects, (4) short biographies of the experts, and (5) the aggregated results of their responses.

  5. Probabilistic accident consequence uncertainty analysis -- Late health effects uncertain assessment. Volume 2: Appendices

    Energy Technology Data Exchange (ETDEWEB)

    Little, M.P.; Muirhead, C.R. [National Radiological Protection Board (United Kingdom); Goossens, L.H.J.; Kraan, B.C.P.; Cooke, R.M. [Delft Univ. of Technology (Netherlands); Harper, F.T. [Sandia National Labs., Albuquerque, NM (United States); Hora, S.C. [Univ. of Hawaii, Hilo, HI (United States)

    1997-12-01

    The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in 1990. These codes estimate the consequence from the accidental releases of radiological material from hypothesized accidents at nuclear installations. In 1991, the US Nuclear Regulatory Commission and the Commission of the European Communities began cosponsoring a joint uncertainty analysis of the two codes. The ultimate objective of this joint effort was to systematically develop credible and traceable uncertainty distributions for the respective code input variables. A formal expert judgment elicitation and evaluation process was identified as the best technology available for developing a library of uncertainty distributions for these consequence parameters. This report focuses on the results of the study to develop distribution for variables related to the MACCS and COSYMA late health effects models. This volume contains appendices that include (1) a summary of the MACCS and COSYMA consequence codes, (2) the elicitation questionnaires and case structures, (3) the rationales and results for the expert panel on late health effects, (4) short biographies of the experts, and (5) the aggregated results of their responses.

  6. Probabilistic accident consequence uncertainty analysis -- Uncertainty assessment for deposited material and external doses. Volume 2: Appendices

    Energy Technology Data Exchange (ETDEWEB)

    Goossens, L.H.J.; Kraan, B.C.P.; Cooke, R.M. [Delft Univ. of Technology (Netherlands); Boardman, J. [AEA Technology (United Kingdom); Jones, J.A. [National Radiological Protection Board (United Kingdom); Harper, F.T.; Young, M.L. [Sandia National Labs., Albuquerque, NM (United States); Hora, S.C. [Univ. of Hawaii, Hilo, HI (United States)

    1997-12-01

    The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in 1990. These codes estimate the consequence from the accidental releases of radiological material from hypothesized accidents at nuclear installations. In 1991, the US Nuclear Regulatory Commission and the Commission of the European Communities began cosponsoring a joint uncertainty analysis of the two codes. The ultimate objective of this joint effort was to systematically develop credible and traceable uncertainty distributions for the respective code input variables. A formal expert judgment elicitation and evaluation process was identified as the best technology available for developing a library of uncertainty distributions for these consequence parameters. This report focuses on the results of the study to develop distribution for variables related to the MACCS and COSYMA deposited material and external dose models. This volume contains appendices that include (1) a summary of the MACCS and COSYMA consequence codes, (2) the elicitation questionnaires and case structures, (3) the rationales and results for the panel on deposited material and external doses, (4) short biographies of the experts, and (5) the aggregated results of their responses.

  7. Probabilistic accident consequence uncertainty analysis -- Uncertainty assessment for internal dosimetry. Volume 2: Appendices

    Energy Technology Data Exchange (ETDEWEB)

    Goossens, L.H.J.; Kraan, B.C.P.; Cooke, R.M. [Delft Univ. of Technology (Netherlands); Harrison, J.D. [National Radiological Protection Board (United Kingdom); Harper, F.T. [Sandia National Labs., Albuquerque, NM (United States); Hora, S.C. [Univ. of Hawaii, Hilo, HI (United States)

    1998-04-01

    The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in 1990. These codes estimate the consequence from the accidental releases of radiological material from hypothesized accidents at nuclear installations. In 1991, the US Nuclear Regulatory Commission and the Commission of the European Communities began cosponsoring a joint uncertainty analysis of the two codes. The ultimate objective of this joint effort was to systematically develop credible and traceable uncertainty distributions for the respective code input variables. A formal expert judgment elicitation and evaluation process was identified as the best technology available for developing a library of uncertainty distributions for these consequence parameters. This report focuses on the results of the study to develop distribution for variables related to the MACCS and COSYMA internal dosimetry models. This volume contains appendices that include (1) a summary of the MACCS and COSYMA consequence codes, (2) the elicitation questionnaires and case structures, (3) the rationales and results for the panel on internal dosimetry, (4) short biographies of the experts, and (5) the aggregated results of their responses.

  8. Preclosure radiological safety analysis for accident conditions of the potential Yucca Mountain Repository: Underground facilities; Yucca Mountain Site Characterization Project

    Energy Technology Data Exchange (ETDEWEB)

    Ma, C.W.; Sit, R.C.; Zavoshy, S.J.; Jardine, L.J. [Bechtel National, Inc., San Francisco, CA (United States); Laub, T.W. [Sandia National Labs., Albuquerque, NM (United States)

    1992-06-01

    This preliminary preclosure radiological safety analysis assesses the scenarios, probabilities, and potential radiological consequences associated with postulated accidents in the underground facility of the potential Yucca Mountain repository. The analysis follows a probabilistic-risk-assessment approach. Twenty-one event trees resulting in 129 accident scenarios are developed. Most of the scenarios have estimated annual probabilities ranging from 10{sup {minus}11}/yr to 10{sup {minus}5}/yr. The study identifies 33 scenarios that could result in offsite doses over 50 mrem and that have annual probabilities greater than 10{sup {minus}9}/yr. The largest offsite dose is calculated to be 220 mrem, which is less than the 500 mrem value used to define items important to safety in 10 CFR 60. The study does not address an estimate of uncertainties, therefore conclusions or decisions made as a result of this report should be made with caution.

  9. Uncertainty and sensitivity analysis in nuclear accident consequence assessment

    International Nuclear Information System (INIS)

    Karlberg, Olof.

    1989-01-01

    This report contains the results of a four year project in research contracts with the Nordic Cooperation in Nuclear Safety and the National Institute for Radiation Protection. An uncertainty/sensitivity analysis methodology consisting of Latin Hypercube sampling and regression analysis was applied to an accident consequence model. A number of input parameters were selected and the uncertainties related to these parameter were estimated within a Nordic group of experts. Individual doses, collective dose, health effects and their related uncertainties were then calculated for three release scenarios and for a representative sample of meteorological situations. From two of the scenarios the acute phase after an accident were simulated and from one the long time consequences. The most significant parameters were identified. The outer limits of the calculated uncertainty distributions are large and will grow to several order of magnitudes for the low probability consequences. The uncertainty in the expectation values are typical a factor 2-5 (1 Sigma). The variation in the model responses due to the variation of the weather parameters is fairly equal to the parameter uncertainty induced variation. The most important parameters showed out to be different for each pathway of exposure, which could be expected. However, the overall most important parameters are the wet deposition coefficient and the shielding factors. A general discussion of the usefulness of uncertainty analysis in consequence analysis is also given. (au)

  10. 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

  11. Reflux esophagitis revisited: Prospective analysis of radiologic accuracy

    International Nuclear Information System (INIS)

    Ott, D.J.; Gelfand, D.W.; Wu, W.C.

    1981-01-01

    A prospective radiologic-endoscopic study of the esophagogastric region in 266 patients, including 206 normals and 60 with esophagitis, is reported. The endoscopic classification grading severity of esophagitis was grade 1-normal; grades 2. 3. and 4-mild, moderate, and severe esophagitis, respectively. Radiology detected 22% of patient with mild esophagitis, 83% with moderate esophagitis, and 95% with severe esophagitis. Although hiatal hernia was present in 40% of normals and 89% with esophagitis, absence of radiographic hiatal hernia excluded esophagitis with 95% accuracy. The implications of this study regarding the role of radiology in evaluating patient with suspected reflux esophagitis are discussed. (orig.) [de

  12. RSVP radiology

    International Nuclear Information System (INIS)

    Kirks, D.R.; Chaffee, D.J.

    1990-01-01

    This paper develops a relative scale of value for pediatric radiology (RSVPR). Neither the HCFA/ACA Relative Value Scale nor the Workload Measurement System developed by Health and Welfare Canada specifically addressed pediatric radiologic examinations. Technical and professional charges for examinations at Children's Hospital Medical Center were reviewed and compared with time and cost analysis. A scale was developed with chest radiography (PA and lateral views) assigned a value of 1. After review by pediatric radiologic technologists, radiologic administrators, pediatric radiologists, and chairs of departments of children's hospitals, this proposed scale was modified to reflect more accurately relative value components of pediatric radiologic and imaging examinations

  13. Radiological Source Terms for Tank Farms Safety Analysis

    Energy Technology Data Exchange (ETDEWEB)

    COWLEY, W.L.

    2000-06-27

    This document provides Unit Liter Dose factors, atmospheric dispersion coefficients, breathing rates and instructions for using and customizing these factors for use in calculating radiological doses for accident analyses in the Hanford Tank Farms.

  14. Method for the analysis pre and post radiological emergency (MAPPER)

    International Nuclear Information System (INIS)

    Perez Velazquez, R.S.; Perez Gonzalez, F.; Fornet Rodriguez, O.; Mustelier Echavarria, A.; Miller Clemente, R.A.

    1998-01-01

    Everything practices associated to the employment he/she gives ionizing radiations it generates a risk, and therefore the possibility exists potentially, he/she gives occurrences he/she gives a radiological accident. Assisting it, all the entities where the nuclear techniques are applied, they should have a method that allows them to evaluate, before y/o after having happened a radiological accident, if the planning and preparation to face emergencies give this it is or it has been effective

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

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  16. A radiologic analysis of hysterosalpinggographic finding in infertility

    International Nuclear Information System (INIS)

    Choi, Hae Young; Lee, Kyung Ja; Yoo, Seong Yul; Kim, Hee Seup

    1985-01-01

    Hysterosalpingography has been universally accepted and approved as valuable aid in the diagnosis and treatment of infertility. Radiologic and clinical analysis had been made on 200 cases of known infertile patient in Ewha Womans University Hospital from January, 1976 to August, 1979. The results are as followings: 1. In 200 cases of infertility, 90 cases (45.5%) are primary infertility and remaining 110 cases (55.5%) are secondary infertility. 2. The peak number of age distribution is 2nd decade group in 115 cases (57.5%). 3. The peak number of duration of infertility is less than 3 years in 107 cases (53,5%). 4. Abnormal uterine finding is 25 cases (12.5%) and there 4 cases (2.0%) of congenital anomaly among them. 5. Abnormal tubal finding is 120 cases (60.0%) and there are 84 cases (42.0%) of without spillage, 36 cases (18.0%) of with spillage, 51 cases (25.5%) of hydrosalpinx, 49 cases (24.5%) of simple obstruction among them. 6. Intravasation is noted in 66 cases (33.3%) among 200 cases. 7. There are significant results between the past history and the hysterosalpiingographic findings by the statistical approach. 8. Pregnancy after hysterosalpingography is noted in 16 cases (8.0%) among 200 cases.

  17. Medical SisRadiologia: a new software tool for analysis of radiological accidents and incidents in medical radiology

    International Nuclear Information System (INIS)

    Lima, Camila M. Araujo; Silva, Francisco C.A. da; Araujo, Rilton A.; Pelegrineli, Samuel Q.

    2013-01-01

    The man's exposure to ionizing radiation in health are has increased considerably due not only the great request of medical examinations as well as the improvement of the techniques used in diagnostic imaging, for example, equipment for conventional X-rays, CT scans, mammography, hemodynamic and others. Although the benefits of using of radiology techniques are unquestionable, the lack of training in radiation protection of the workers, associated with procedure errors, have been responsible for the increasing number of radiation overexposures of these workers. Sometimes these high doses are real and there is a true radiological accident. The radiation workers, named occupationally Exposed Individual (IOE), must comply with two national regulations: Governmental Decree 453/1998 of the National Agency of Sanitary Surveillance (Portaria 453/1998 ANVISA Agencia Nacional de Vigilancia Sanitaria), which establishes the basic guidelines for radiation protection in medial and dental radiology and; the Governmental Decree NR-32/2002 of the Ministry of Labour and Employment (Ministerio do Trabalho e Emprego), which establishes the basic guidelines for the worker's health. The two mandatory regulations postulate a detailed investigation in the event of radiation overexposure of an IOE. In order to advice the diagnostic institution to perform an efficient analysis, investigation and report of high doses, it is proposed the use of a computational tool named 'Medical SisRadiologia'. This software tool enables the compilation and record of radiological abnormal data occurred in a diagnostic institution. It will also facilitate the detailed analysis of the event and will increase the effectiveness and development of work performed by the Radiation Protection Service. At the end, a technical report is issued, in accordance with the regulations of the technical regulations, which could also be used as training tool to avoid another event in the future. (author)

  18. Medical SisRadiologia: a new software tool for analysis of radiological accidents and incidents in medical radiology

    Energy Technology Data Exchange (ETDEWEB)

    Lima, Camila M. Araujo; Silva, Francisco C.A. da, E-mail: araujocamila@yahoo.com.br, E-mail: dasilva@ird.gov.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Araujo, Rilton A.; Pelegrineli, Samuel Q., E-mail: consultoria@maximindustrial.com.br, E-mail: samuelfisica@maximindustrial.com.br [Maxim Industrial, Rio de Janeiro, RJ (Brazil)

    2013-07-01

    The man's exposure to ionizing radiation in health are has increased considerably due not only the great request of medical examinations as well as the improvement of the techniques used in diagnostic imaging, for example, equipment for conventional X-rays, CT scans, mammography, hemodynamic and others. Although the benefits of using of radiology techniques are unquestionable, the lack of training in radiation protection of the workers, associated with procedure errors, have been responsible for the increasing number of radiation overexposures of these workers. Sometimes these high doses are real and there is a true radiological accident. The radiation workers, named occupationally Exposed Individual (IOE), must comply with two national regulations: Governmental Decree 453/1998 of the National Agency of Sanitary Surveillance (Portaria 453/1998 ANVISA Agencia Nacional de Vigilancia Sanitaria), which establishes the basic guidelines for radiation protection in medial and dental radiology and; the Governmental Decree NR-32/2002 of the Ministry of Labour and Employment (Ministerio do Trabalho e Emprego), which establishes the basic guidelines for the worker's health. The two mandatory regulations postulate a detailed investigation in the event of radiation overexposure of an IOE. In order to advice the diagnostic institution to perform an efficient analysis, investigation and report of high doses, it is proposed the use of a computational tool named 'Medical SisRadiologia'. This software tool enables the compilation and record of radiological abnormal data occurred in a diagnostic institution. It will also facilitate the detailed analysis of the event and will increase the effectiveness and development of work performed by the Radiation Protection Service. At the end, a technical report is issued, in accordance with the regulations of the technical regulations, which could also be used as training tool to avoid another event in the future. (author)

  19. 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

  20. Time analysis for optimization of radiology workflow in conventional radiology during RIS-PACS-integration

    Science.gov (United States)

    Falkensammer, Peter; Soegner, Peter I.; zur Nedden, Dieter

    2002-05-01

    The integration of RIS-PACS systems in radiology units are intended to reduce time consumption in radiology workflow and thus to increase radiologist productivity. Along with the RIS-PACS integration at the University Hospital Innsbruck we analyzed workflow from patient admission to release of final reports before implementation. The follow up study after six months of the implementation is currently in work. In this study we compared chest to skeletal x-ray examinations in 969 patients before the implementation. Drawing the admission-to-release-of-final-report period showed a two-peak diagram with the first peak corresponding to a release of final results on the same day and the second peak to a release on the following day. In the chest x-ray group, 57% were released the same day (mean value 4:02 hours) and 43% the next day (mean value 21:47 hours). Looking at the skeletal x-rays 40% were released the same day (mean value 3:58 hours) and 60% were released the next day (mean value 21:05 hours). Summarizing the results we should say, that the average chest x-ray requires less time than an skeletal x-ray, due to the fact that a greater percentage of reports is released the same day. The most important result is, that the most time consuming workstep is the exchange of data media between radiologist and secretary with at least 5 hours.

  1. An assessment of the Canadian Forces' capability to manage the consequences of the domestic use of chemical, biological, radiological or nuclear weapons of mass destruction

    International Nuclear Information System (INIS)

    Pickering, W.L.

    2003-01-01

    In view of the threat to Canadian domestic targets presented by the asymmetric use of chemical, biological, radiological or nuclear (CBRN) weapons of mass destruction (WMD), this thesis examines whether the Canadian Forces (CF) has capability deficiencies in managing the consequences of such an attack. Research included an examination of the post Cold War strategic environment, the state of the art in CBRN technology, current concepts and experience in managing the consequences of major disasters and responsibilities at the municipal, provincial and federal levels of government. The methodology used included scenario based planning to develop circumstances where WMD might be used domestically, and decomposition to break down the scenarios into events and potential CF roles and tasks. The current CF structure was used to determine the probable CF response, which included the ability of CF units to perform the required tasks, the CF response time and the ability of the CF to sustain the operation. (author)

  2. Needle stick injury in a radiology department: a decade analysis

    International Nuclear Information System (INIS)

    Sayani, R.; Rajani, A.

    2012-01-01

    Objectives: To determine the frequency of needle stick injury in health care workers of radiology department. Study type, settings and duration: Cross sectional, observational study conducted at the Radiology department of Aga Khan University hospital from January 2000 to May 2010. Subject and Methods: All self-reported needle stick injuries data of Health care workers of radiology department was recorded. The personnel involved (Radiologist, resident, radiographer, nurses etc), area of working and the causes of injury were identified including the procedural or post procedural details. Patient's status of hepatitis or blood borne infection was also noted. Data was recorded and analyzed in Excel worksheet. Results: A total of 55 health workers reported needle stick injuries at all sections of radiology departments with maximum number needle stick injuries at general radiography, fluoroscopy and IVP section. Radiographers and radiology residents received the maximum number of injuries. Major cause of injury was cannulation however, many injuries occurred during disposing or handling of bin. In majority of cases the patients were not infected with any known blood borne infections. Conclusions: Doctors and nurses get needle-stick injuries while carrying out clinical procedures, while, ancillary staff get infected post procedure during disposal of garbage. Policy message: Good occupational health and safety practices must be promoted to all staff. Safer disposal of needles is an important area where practice and procedure needs to be carefully reviewed. It is necessary to undertake a risk assessment, to offer counseling and Post Exposure Prophylaxis and treatment where necessary. (author)

  3. RaCon: a software tool serving to predict radiological consequences of various types of accident in support of emergency management and radiation monitoring management

    International Nuclear Information System (INIS)

    Svanda, J.; Hustakova, H.; Fiser, V.

    2008-01-01

    The RaCon software system, developed by the Nuclear Research Institute Rez, is described and its application when addressing various tasks in the domain of radiation accidents and nuclear safety (accidents at nuclear facilities, transport of radioactive material, terrorist attacks) are outlined. RaCon is intended for the prediction and evaluation of radiological consequences to population and rescue teams and for optimization of monitoring actions. The system provides support to emergency management when evaluating and devising actions to mitigate the consequences of radiation accidents. The deployment of RaCon within the system of radiation monitoring by mobile emergency teams or remote controlled UAV is an important application. Based on a prediction of the radiological situation, RaCon facilitates decision-making and control of the radiation monitoring system, and in turn, refines the prediction based on observed values. Furthermore, the system can perform simulations of evacuation patterns at the Dukovany NPP and at schools in the vicinity of the power plant and can provide support to emergency management should any such situation arise. (orig.)

  4. Intermediate and long-term radiological consequences of an uncontrolled access of saline solution into the Asse mine - 59163

    International Nuclear Information System (INIS)

    Ustohalova, Veronika; Kueppers, Christian

    2012-01-01

    The risk of radioactive contamination in the biosphere surrounding the Asse salt mine has been assessed to determine the possible radioactive exposure to humans if the mine collapses. Geological conditions and anthropogenic activities have made the mine instable and allow salt-saturated ground water to seep in. This uncontrolled brine inflow significantly increases the risk of the mine collapsing. If the mine collapses, the brine will be pressed into groundwater, where the radionuclides can migrate into the biosphere and cause radioactive exposure. The key issue discussed in this paper is estimating the short- and long-term radiation burden for humans under several possible scenarios of radionuclide release. Only a radioecological model able to quantify and estimate processes taking place can generate usable results. This work develops the radioecological model describing both radionuclide migration and the resulting radiological exposure along several exposition pathways. Development of the model took into account the sorption processes, solubility limits and special aspects of decay chain migration. The radiological exposure was estimated under non-equilibrated conditions for the case of short-time expositions. At the end of this paper, the model's background, the results of the computations and a comparison of several scenarios will be presented. The estimating short- and long-term radiation burden for humans under several possible scenarios of radionuclide release in the biosphere surrounding the Asse salt mine is the key issue for further planning of suitable decommissioning options. In the case that the mine collapses, the radionuclide can be pressed out into groundwater and migrate into the biosphere. A radioecological model consisting of two independent tools -- radionuclide migration in groundwater ('Migration') and resulting radiological exposure along several pathways ('Exposure') - was developed. The radionuclide migration can be computed with the

  5. Standarized radiological hazard analysis for a broad based operational safety program

    International Nuclear Information System (INIS)

    Wadman, W.W. III; Andrews, L.L.

    1992-01-01

    The Radiological hazard Analysis (RHA) Manual provides a methodology and detailed guidance for systematic analysis of radiological hazards over a broad spectrum of program functions, housed in a wide variety of facilities. Radiological programs at LANL include: research and experimentation; routine materials operations; production; non-destructive examination or testing; isotope and machine produced radiations; chemistry; and metallurgy. The RHA permits uniform evaluation of hazard types over a range of several orders of magnitude of hazard severity. The results are used to estimate risk, evaluate types and level or resource allocations, identify deficiencies, and plan corrective actions for safe working environments. 2 refs

  6. Standardized radiological hazard analysis for a broad based operational safety program

    International Nuclear Information System (INIS)

    Wadman, W. III; Andrews, L.

    1992-01-01

    The Radiological Hazard Analysis (RHA) Manual provides a methodology and detailed guidance for systematic analysis of radiological hazards over a broad spectrum of program functions, housed in a wide variety of facilities. Radiological programs at LANL include: research and experimentation routine materials operations; production; non-destructive examination or testing; isotope and machine produced radiations; chemistry; and metallurgy. The RHA permits uniform evaluation of hazard types over a range of several orders of magnitude of hazard severity. The results are used to estimate risk, evaluate types and level of resource allocations, identify deficiencies, and plan corrective actions for safe working environments. (author)

  7. Consequence analysis and probabilistic safety analysis of Angra-1

    International Nuclear Information System (INIS)

    Guimaraes, A.C.F.

    1987-07-01

    A methodology for determining the environmental consequences in the site of nuclear power plants, is presented. The methodology obtains as final result the 'S' site matrix, which represents the probabilities of health damage. Two types of healt damages were analysed: the early fatalities and injury. The damages are calculated from the determination of radiation doses which the population in surrounding of the site could be submitted, in the case of severe accident with the core meltdown. The accidents are defined from an initial event, leading to the failure of reactor containment. The results presented the same magnitude order when they were compared with ones obtained in studies of the Zion Nuclear Power Plant. The Angra-1 was adopted as reference reactor and the CRAC-2 computer code was used. (M.C.K.) [pt

  8. Estimation of the Radiological Consequences of Fukushima Dai-ichi Nuclear Power Plant Accident using MACCS2

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sora; Min, Byung-Il; Park, Kihyun; Yang, Byung-Mo; Suh, Kyung-suk [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    Three of them have undergone fuel melting and hydrogen explosions. A significant amount of radioactive material was released into the atmosphere from FDNPP and dispersed all over the world. In this study, we assessed the offsite consequences of Fukushima disaster in the region within a 30-km radius of FDNPP using the MELCOR Accident Consequence Code Systems 2(MACCS2) code, which is the Nuclear Regulatory Commission's (NRC's) code. The reflection of the realistic regional characteristics, such as long-term meteorological data, site- and population-specific data, and radiation safety regulatory, is essential to accurately analyze the off-site consequences. The assessment that reflects regional characteristics would contribute to identify main causes of exposure doses and to find the effective countermeasures for minimizing the accidental off-site consequences.

  9. Gender Trends in Radiology Authorship: A 35-Year Analysis.

    Science.gov (United States)

    Piper, Crystal L; Scheel, John R; Lee, Christoph I; Forman, Howard P

    2016-01-01

    The purpose of this study was to describe trends over time in female authorship in the radiology literature and to investigate the tendency of female first authors to publish with female senior authors. Data on the gender of academic physician authors based in the United States for all major articles published in three general radiology journals--Radiology, AJR, and Academic Radiology--were collected and analyzed for the years 1978, 1988, 1998, 2008, and 2013. Multivariate logistic regression was used to identify significant trends over time, and a chi-square test of independence was performed to determine significant relations between the genders of first and senior authors. The gender of 4182 of 4217 (99.17%) authors with MD degrees was determined. The proportion of original research articles published by women as first authors increased from 8.33% in 1978 to 32.35% in 2013 (p < 0.001). The proportion of original research articles with women as senior authors increased from 6.75% in 1978 to 21.90% in 2013 (p < 0.001). Female first and senior authorship increased significantly over time (first author, p < 0.001; senior author, p < 0.001). There was a statistically significant relation between the genders of first and senior authors of original research articles and guest editorials (p < 0.001). Over 35 years, there was a statistically significant upward linear trend of female physician participation in authorship of academic radiology literature. Female first authors were more likely to publish with female senior authors.

  10. Radiological consequences of floods in december 2003 in small Camargue at the place known as the Claire Farine. Results of the assessment realised at the demand of the C.L.I. of the Gard; Consequences radiologiques des inondations de decembre 2003 en petite Camargue au lieu dit Claire Farine. Resultats de l'expertise realisee a la demande de la CLI du Gard

    Energy Technology Data Exchange (ETDEWEB)

    Eyrolle, F.; Duffa, C.; Leprieur, F.; Rolland, B.; Antonelli, C.; Marquet, J.; Saleun, G.; Renaud, Ph

    2004-05-15

    The levels of activities measured in the market gardening are not significantly different from these ones measured in the similar samples that did not received the floods in december 2003. The results of chemical analysis do not show contamination of soils and market gardening. In conclusion, the results of assessment show that the floods of december 2003 in small Camargue at the place called 'Claire Farine) had no significant radiological and chemical consequences. (N.C.)

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

    International Nuclear Information System (INIS)

    Zarnowiecki, K.

    1988-01-01

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

  12. Report of the preliminary mission of radiological controls on the island of Mangareva and the atolls of Tureia and Hao (French Polynesia). Investigation performed by the CRIIRAD laboratory on the request of the inquiry Commission on consequences of atmospheric nuclear tests

    International Nuclear Information System (INIS)

    2006-01-01

    After a presentation of the objectives of the mission, and a summary of the undertaken actions on each site, this document gives some general information on radionuclides and on the sampling and analysis method. Then, it discusses the results obtained by radiological analyses and gives recommendations about the current radiological situation of the studied island and atolls. It shows that official assessment of radiation doses undergone by the French Polynesia population during the period atmospheric nuclear tests must be revised. It outlines the need of new exhaustive investigations on health consequences of these past exposures to ionizing radiation. Recommendations are formulated

  13. Digital radiology

    International Nuclear Information System (INIS)

    Dallas, W.J.

    1990-01-01

    Radiology is vital to the life-saving efforts of surgeons and other physicians, but precious time can be lost generating the images and transferring them to and from the operating room. Furthermore, hospitals are straining under the task of storing and managing the deluge of diagnostic films produced every year. A 300-bed hospital generates about 1 gigabyte (8 x 10 9 bits) of picture information every day and is legally bound to hold it for three to seven years--30 years in the case of silicosis or black lung disease, illnesses that may have relevance to future lawsuits. Consequently, hospital warehouses are filling with x-ray film and written reports that are important for analysis of patient histories, for comparison between patients, and for analyzing the progress of disease. Yet only a fraction of the information's potential is being used because access is so complicated. What is more, films are easily lost, erasing valuable medical histories

  14. An uncertainty analysis using the NRPB accident consequence code Marc

    International Nuclear Information System (INIS)

    Jones, J.A.; Crick, M.J.; Simmonds, J.R.

    1991-01-01

    This paper describes an uncertainty analysis of MARC calculations of the consequences of accidental releases of radioactive materials to atmosphere. A total of 98 parameters describing the transfer of material through the environment to man, the doses received, and the health effects resulting from these doses, was considered. The uncertainties in the numbers of early and late health effects, numbers of people affected by countermeasures, the amounts of food restricted and the economic costs of the accident were estimated. This paper concentrates on the results for early death and fatal cancer for a large hypothetical release from a PWR

  15. Accident consequence calculations for project W-058 safety analysis

    International Nuclear Information System (INIS)

    Van Keuren, J.C.

    1997-01-01

    This document describes the calculations performed to determine the accident consequences for the W-058 safety analysis. Project W-058 is the replacement cross site transfer system (RCSTS), which is designed to transort liquid waste between the 200 W and 200 E areas. Calculations for RCSTS safety analyses used the same methods as the calculations for the Tank Waste Remediation System (TWRS) Basis for Interim Operation (BIO) and its supporting calculation notes. Revised analyses were performed for the spray and pool leak accidents since the RCSTS flows and pressures differ from those assumed in the TWRS BIO. Revision 1 of the document incorporates review comments

  16. Uncertainty Analysis of Consequence Management (CM) Data Products.

    Energy Technology Data Exchange (ETDEWEB)

    Hunt, Brian D. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Eckert-Gallup, Aubrey Celia [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Cochran, Lainy Dromgoole [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Kraus, Terrence D. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Fournier, Sean Donovan [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Allen, Mark B. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Schetnan, Richard Reed [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Simpson, Matthew D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Okada, Colin E. [Remote Sensing Lab. (RSL), Nellis AFB, Las Vegas, NV (United States); Bingham, Avery A. [Remote Sensing Lab. (RSL), Nellis AFB, Las Vegas, NV (United States)

    2018-01-01

    The goal of this project is to develop and execute methods for characterizing uncertainty in data products that are deve loped and distributed by the DOE Consequence Management (CM) Program. A global approach to this problem is necessary because multiple sources of error and uncertainty from across the CM skill sets contribute to the ultimate p roduction of CM data products. This report presents the methods used to develop a probabilistic framework to characterize this uncertainty and provides results for an uncertainty analysis for a study scenario analyzed using this framework.

  17. Radiological analysis of polyostotic fibrous dysplasia in skeletal system

    International Nuclear Information System (INIS)

    Shin, Ma Rie; Kim, Jin Sik; Kim, Han Suk; Park, Soo Soung

    1984-01-01

    Over a period of recent 3 years, the 5 cases of polyostotic fibrous dysplasia were proven histologically at National Medical Center, and they were evaluated and analyzed radiologically and clinically. The results were as follows: 1. The age of 5 patients ranged from 12 to 21. 2. In general, clinical symptoms of these patients were pain of affected sites and swelling , fracture, walking disturbance of lower extremities. 3. The order of frequent site of polyostotic fibrous dysplasia was skull (4 cases), femur (3 cases), maxilla (2 case), humerus, tibia, rib, radius, metacarpal bone and phalanx. 4. The characteristic radiological findings of polyostotic fibrous dysplasia were multicystic lesions with ground glass appearance, osteosclerosis, cortical thinning and pathologic fracture and deformity of long bones. Particularly, in the extremities, multicystic radiolucencies, groud glass appearance, shepherd's crook and coxa vara deformities were noticed, and in the skull and maxilla, sclerotic changes were principally demonstrated.

  18. Common fluoroscopic studies in radiology : conduct and analysis method

    International Nuclear Information System (INIS)

    Valverde Sanchez, Allan

    2011-01-01

    A countless number of radiological procedures, that have involved the use of fluoroscopy and contrast media of different indole, have been carried out in all radiology services and medical images of Costa Rica for the diagnosis of diseases or conditions, in both adults and in children. Fluoroscopic studies, often called special or contrast studies, have had particular conditions for its realization. Some from the medical point of view: adequate training in the technical and cognitive development when evaluating the images to not miss important details. Other by the patient: adequate preparation to achieve the best images for optimal diagnosis. For example, adequate bowel preparation is essential for a barium enema, to cooperation by the patient to meet specific indications that the physician dictates when swallowing postures or just when you are prompted. Criteria have been met and unified for contrast studies in different hospitals and clinics. The indications, contra, method, technique of procedure, points to remember, number of images or projections minimum required in the interpretation of contrast studies, as well as a report template of standard and ideal study are presented in a simple, systematic and logical. The manual is intended for residents and attending physicians specialists in radiology and medical imaging including contrast studies more common. Spaces are promoted with current technology studies to set aside more complicated and less sophisticated as have been the fluoroscopic studies; however, in the national reality, access to computerized tomography and magnetic resonance imaging is not as easy. Radiological studies with fluoroscopy performed by trained staff led the treating physician to make sound decisions based on studies relatively simple and easy to do. The tests with the use of fluoroscopic have been named: the esophagogram, gastroduodenal series, gastro intestinal transit, the hysterosalpingography, the cystography and the

  19. Radiological consequences of the Fukushima event via water pathways. Background on dose calculations for fish and seaweed consumption

    International Nuclear Information System (INIS)

    Schmidt, Gerhard

    2011-01-01

    In connection with the accident in Fukushima large amounts of highly contaminated water seeped through the structures of the buildings of Unit 2, collected on lower levels of the reactor buildings, and made their way to rooms on lower levels of the turbine building. This paper quantifies the data, that is measured by TEPCO, adds calculated doses for selected pathways, and draws conclusions from this data and doses in respect to short- and longer term conse-quences.

  20. Non-radiological consequences to the aquatic biota and fisheries of the Susquehanna River from the 1979 accident at Three Mile Island Nuclear Station

    International Nuclear Information System (INIS)

    Hickey, C.R. Jr.; Samworth, R.B.

    1979-11-01

    The non-radiological consequences to the aquatic biota and fishes of the Susquehanna River from the March 28, 1979 accident at Three Mile Island Nuclear Station were assessed through the post-accident period of July 1979. Thermal and chemical discharges during the period did not exceed required effluent limitations. Several million gallons of treated industrial waste effluents were released into the river which were not of unusual volumes compared with normal operation and were a very small proportion of the seasonally high river flows. The extent and relative location of the effluent plume were defined and the fisheries known to have been under its immediate influence were identified, including rough, forage, and predator/sport fishery species

  1. Radiological consequence analyses of loss of coolant accidents of various break sizes of Pressurized Heavy Water Reactor

    International Nuclear Information System (INIS)

    Sanyasi Rao, V.V.S.; Hari Prasad, M.; Ghosh, A.K.

    2010-01-01

    For any advanced technology, it is essential to ensure that the consequences associated with the accident sequences arising, if any, from the operation of the plant are as low as possible and certainly below the guidelines/limits set by the regulatory bodies. Nuclear power is no exception to this. In this paper consequences of the events arising from Loss of Coolant Accident (LOCA) sequences in Pressurized Heavy Water Reactor (PHWR), are analysed. The sequences correspond to different break sizes of LOCA followed by the operation or otherwise of Emergency Core Cooling System (ECCS). Operation or otherwise of the containment safety systems has also been considered. It has been found that there are no releases to the environment when ECCS is available. The releases, when ECCS is not available, arise from the slack and the ground. The radionuclides considered include noble gases, iodine, and cesium. The hourly meteorological parameters (wind speed, wind direction, precipitation and stability category), considered for this study, correspond to those of Kakrapar site. The consequences evaluated are the thyroid dose and the bone marrow dose received by a person located at various distances from the release point. Isodose curves are generated. From these evaluations, it has been found that the doses are very low. The complementary cumulative frequency distributions (CCFD) for thyroid and bone marrow doses have also been presented for the cases analysed. (author)

  2. Inverse modelling for real-time estimation of radiological consequences in the early stage of an accidental radioactivity release.

    Science.gov (United States)

    Pecha, Petr; Šmídl, Václav

    2016-11-01

    A stepwise sequential assimilation algorithm is proposed based on an optimisation approach for recursive parameter estimation and tracking of radioactive plume propagation in the early stage of a radiation accident. Predictions of the radiological situation in each time step of the plume propagation are driven by an existing short-term meteorological forecast and the assimilation procedure manipulates the model parameters to match the observations incoming concurrently from the terrain. Mathematically, the task is a typical ill-posed inverse problem of estimating the parameters of the release. The proposed method is designated as a stepwise re-estimation of the source term release dynamics and an improvement of several input model parameters. It results in a more precise determination of the adversely affected areas in the terrain. The nonlinear least-squares regression methodology is applied for estimation of the unknowns. The fast and adequately accurate segmented Gaussian plume model (SGPM) is used in the first stage of direct (forward) modelling. The subsequent inverse procedure infers (re-estimates) the values of important model parameters from the actual observations. Accuracy and sensitivity of the proposed method for real-time forecasting of the accident propagation is studied. First, a twin experiment generating noiseless simulated "artificial" observations is studied to verify the minimisation algorithm. Second, the impact of the measurement noise on the re-estimated source release rate is examined. In addition, the presented method can be used as a proposal for more advanced statistical techniques using, e.g., importance sampling. Copyright © 2016 Elsevier Ltd. All rights reserved.

  3. Health effects models for nuclear power plant accident consequence analysis

    International Nuclear Information System (INIS)

    Abrahamson, S.; Bender, M.A.; Boecker, B.B.; Scott, B.R.

    1993-05-01

    The Nuclear Regulatory Commission (NRC) has sponsored several studies to identify and quantify, through the use of models, the potential health effects of accidental releases of radionuclides from nuclear power plants. The Reactor Safety Study provided the basis for most of the earlier estimates related to these health effects. Subsequent efforts by NRC-supported groups resulted in improved health effects models that were published in the report entitled open-quotes Health Effects Models for Nuclear Power Plant Consequence Analysisclose quotes, NUREG/CR-4214, 1985 and revised further in the 1989 report NUREG/CR-4214, Rev. 1, Part 2. The health effects models presented in the 1989 NUREG/CR-4214 report were developed for exposure to low-linear energy transfer (LET) (beta and gamma) radiation based on the best scientific information available at that time. Since the 1989 report was published, two addenda to that report have been prepared to (1) incorporate other scientific information related to low-LET health effects models and (2) extend the models to consider the possible health consequences of the addition of alpha-emitting radionuclides to the exposure source term. The first addendum report, entitled open-quotes Health Effects Models for Nuclear Power Plant Accident Consequence Analysis, Modifications of Models Resulting from Recent Reports on Health Effects of Ionizing Radiation, Low LET Radiation, Part 2: Scientific Bases for Health Effects Models,close quotes was published in 1991 as NUREG/CR-4214, Rev. 1, Part 2, Addendum 1. This second addendum addresses the possibility that some fraction of the accident source term from an operating nuclear power plant comprises alpha-emitting radionuclides. Consideration of chronic high-LET exposure from alpha radiation as well as acute and chronic exposure to low-LET beta and gamma radiations is a reasonable extension of the health effects model

  4. The concept of validation of numerical models for consequence analysis

    International Nuclear Information System (INIS)

    Borg, Audun; Paulsen Husted, Bjarne; Njå, Ove

    2014-01-01

    Numerical models such as computational fluid dynamics (CFD) models are increasingly used in life safety studies and other types of analyses to calculate the effects of fire and explosions. The validity of these models is usually established by benchmark testing. This is done to quantitatively measure the agreement between the predictions provided by the model and the real world represented by observations in experiments. This approach assumes that all variables in the real world relevant for the specific study are adequately measured in the experiments and in the predictions made by the model. In this paper the various definitions of validation for CFD models used for hazard prediction are investigated to assess their implication for consequence analysis in a design phase. In other words, how is uncertainty in the prediction of future events reflected in the validation process? The sources of uncertainty are viewed from the perspective of the safety engineer. An example of the use of a CFD model is included to illustrate the assumptions the analyst must make and how these affect the prediction made by the model. The assessments presented in this paper are based on a review of standards and best practice guides for CFD modeling and the documentation from two existing CFD programs. Our main thrust has been to assess how validation work is performed and communicated in practice. We conclude that the concept of validation adopted for numerical models is adequate in terms of model performance. However, it does not address the main sources of uncertainty from the perspective of the safety engineer. Uncertainty in the input quantities describing future events, which are determined by the model user, outweighs the inaccuracies in the model as reported in validation studies. - Highlights: • Examine the basic concept of validation applied to models for consequence analysis. • Review standards and guides for validation of numerical models. • Comparison of the validation

  5. Comprehensive analysis of a Radiology Operations Management computer system.

    Science.gov (United States)

    Arenson, R L; London, J W

    1979-11-01

    The Radiology Operations Management computer system at the Hospital of the University of Pennsylvania is discussed. The scheduling and file room modules are based on the system at Massachusetts General Hospital. Patient delays are indicated by the patient tracking module. A reporting module allows CRT/keyboard entry by transcriptionists, entry of standard reports by radiologists using bar code labels, and entry by radiologists using a specialty designed diagnostic reporting terminal. Time-flow analyses demonstrate a significant improvement in scheduling, patient waiting, retrieval of radiographs, and report delivery. Recovery of previously lost billing contributes to the proved cost effectiveness of this system.

  6. Accident consequence calculations for project W-058 safety analysis

    International Nuclear Information System (INIS)

    Van Keuren, J.C.

    1997-01-01

    Accident consequence analyses have been performed for Project W-058, the Replacement Cross Site Transfer System. using the assumption and analysis techniques developed for the Tank Remediation Waste system Basis for Interim Operation. most potential accident involving the FISTS are bounded by the TWRS BIO analysis. However, the spray leak and pool leak scenarios require revised analyses since the RCSTS design utilizes larger diameter pipe and higher pressures than those analyzed in the TWRS BIO. Also the volume of diversion box and vent station are larger than that assumed for the valve pits in the TWRS BIO, which effects results of sprays or spills into the pits. the revised analysis for the spray leak is presented in Section 2, for the above ground spill in Section 3, for the presented in Section 2, for the above ground spill in Section 3, for the subsurface spill forming a pool in Section 4, and for the subsurface pool remaining subsurface in Section 5. The conclusion from these sections are summarized below

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

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  8. 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)

  9. Analysis of factors correlating with medical radiological examination frequencies

    International Nuclear Information System (INIS)

    Jahnen, A.; Jaervinen, H.; Bly, R.; Olerud, H.; Vassilieva, J.; Vogiatzi, S.; Shannoun, F.

    2015-01-01

    The European Commission (EC) funded project Dose Datamed 2 (DDM2) had two objectives: to collect available data on patient doses from the radiodiagnostic procedures (X-ray and nuclear medicine) in Europe, and to facilitate the implementation of the Radiation Protection 154 Guidelines (RP154). Besides the collection of frequency and dose data, two questionnaires were issued to gather information about medical radiological imaging. This article analyses a possible correlation between the collected frequency data, selected variables from the results of the detailed questionnaire and national economic data. Based on a 35 countries dataset, there is no correlation between the gross domestic product (GDP) and the total number of X-ray examinations in a country. However, there is a significant correlation ( p < 0.01) between the GDP and the overall CT examination frequency. High income countries perform more CT examinations per inhabitant. That suggests that planar X-ray examinations are replaced by CT examinations. (authors)

  10. Radiologic analysis of femoral acetabular impingement: from radiography to MRI

    Energy Technology Data Exchange (ETDEWEB)

    Dwek, Jerry R. [University of California at San Diego, Department of Radiology, Rady Children' s Hospital and Health Center, San Diego, CA (United States); San Diego Imaging, San Diego, CA (United States); Monazzam, Shafagh [Rady Children' s Hospital and Health Center, Department of Orthopedics, San Diego, CA (United States); Chung, Christine B. [University of California at San Diego, Department of Radiology, San Diego, CA (United States)

    2013-03-15

    Femoral acetabular impingement is a set of morphologic abnormalities that are considered to be a major cause of degenerative disease in the hip joint. Early changes are already present in adolescence when it is the pediatric radiologist who must assess current damage with the aim of averting progression to more severe and debilitating osteoarthritis. A multimodality approach is used for diagnosis, that includes conventional radiography and CT to assess the osseous structures. MR arthrography is the primary advanced imaging modality for assessment of morphologic changes as well as injuries of the labrum and articular cartilage. Details of radiologic imaging are offered to guide the radiologist and provide an avenue for the accurate description of the osseous and articular alterations and injury. (orig.)

  11. Diagnostic radiology for functional analysis of the cervical vertebral column

    International Nuclear Information System (INIS)

    Kamieth, H.

    1986-01-01

    The book is averaged in 17 chapters. The first three, introductory chapters dealing with the significance of radiology for the functional diagnosis of the cervical spine are followed by three chapters discussing the movements of the atlantoaxial joints, the statics of the cervical spine, and the sagittal flexural movements in the C2-C7 segments. Subsequent chapters discuss the radiodiagnostical method according to Arlen, the innervation of the cervical spine segments of movement, disturbances of movement including restriction of movement, degenerative processes of the invertebral disks, and hypermobile disturbance of movement. The final chapters deal with compensational and dissociation phenomena, subluxations, defective or compulsive positions, etc., the causes of each, and with the clinical relevance of spondylochondrosis and arthrosis, and with the pain. With 171 figs [de

  12. The radiology job market: analysis of the ACR jobs board.

    Science.gov (United States)

    Prabhakar, Anand M; Oklu, Rahmi; Harvey, H Benjamin; Harisinghani, Mukesh G; Rosman, David A

    2014-05-01

    The aim of this study was to assess the status of the radiology job market as represented by the ACR Jobs Board from October 2010 to June 2013. With the assistance of the ACR, data from the ACR Jobs Board from October 2010 through June 2013, including the numbers of monthly new job seekers, new job postings, and job posting clicks, were gathered and used to calculate a monthly competitive index, defined as the ratio of new job seekers to new job postings. During the study period, the mean number of new job seekers was 168 per month, which was significantly greater than the 84 average new job postings for any given month (P = .0002). There was no significant difference between 2011 and 2012 with regard to the number of new job seekers or job postings. Over the time period assessed, more new job seekers registered in October and November 2010, August to November 2011, and October and November 2012. These periods were also associated with the highest competitive index values. There were less job seekers in the winter and spring of 2011, 2012, and 2013, periods associated with lower competitive index values. ACR Jobs Board activity, measured by job posting clicks, was significantly higher in 2012 than in 2011 (P Jobs Board, there were consistently more new job seekers than job postings throughout the study period, and fall is the period in the year most associated with the highest competitive index for radiologist employment. Copyright © 2014 American College of Radiology. Published by Elsevier Inc. All rights reserved.

  13. 40 CFR 1400.5 - Internet access to certain off-site consequence analysis data elements.

    Science.gov (United States)

    2010-07-01

    ... consequence analysis data elements. 1400.5 Section 1400.5 Protection of Environment ENVIRONMENTAL PROTECTION... UNDER THE CLEAN AIR ACT SECTION 112(r)(7); DISTRIBUTION OF OFF-SITE CONSEQUENCE ANALYSIS INFORMATION DISTRIBUTION OF OFF-SITE CONSEQUENCE ANALYSIS INFORMATION Public Access § 1400.5 Internet access to certain off...

  14. Data analysis and review of radiology services at Glasgow 2014 Commonwealth Games.

    Science.gov (United States)

    Bethapudi, Sarath; Ritchie, David; Bongale, Santosh; Gordon, Jonny; MacLean, John; Mendl, Liz

    2015-10-01

    Medical services at the Glasgow 2014 Commonwealth Games (CWG) were provided though a purpose-built medical polyclinic, which had a fully equipped radiology department along with other services, set up within the main Games Village. Data analysis of radiology services offered at CWG has not been published before. Imaging services within the polyclinic, Athletes Village, Glasgow 2014 CWG. The aim of the paper is to analyse data on radiological investigations and assess the demand and distribution of workload on imaging services at CWG 2014. Data on radiology investigations at the CWG 2014 was retrieved from the Carestream picture archiving and communication system (PACS) and Pharmasys (CWG official centralised electronic database system) and analysed. Six hundred ninety-seven diagnostic and interventional procedures were performed. Of these 37.9% were magnetic resonance imaging (MRI) scans, 22% were diagnostic ultrasound (US) examinations, 33.1% were radiographs, 4.3% were computed tomography (CT) scans and 2.7% were imaging-guided interventional procedures. 88% of imaging was performed on athletes and the remainder were performed on team officials and workforce. Demand on radiology services gradually picked up through the pre-competition period and peaked half way through the CWG. Radiology played a vital role in the successful provision of medical services at the Glasgow 2014 CWG. High demand on imaging services can be expected at major international sporting events and therefore pre-event planning is vital. Having back-up facilities in case of technical failure should be given due importance when planning radiology services at future CWG events.

  15. Data analysis and review of radiology services at Glasgow 2014 Commonwealth Games

    International Nuclear Information System (INIS)

    Bethapudi, Sarath; Ritchie, David; Bongale, Santosh; Gordon, Jonny; MacLean, John; Mendl, Liz

    2015-01-01

    Medical services at the Glasgow 2014 Commonwealth Games (CWG) were provided though a purpose-built medical polyclinic, which had a fully equipped radiology department along with other services, set up within the main Games Village. Data analysis of radiology services offered at CWG has not been published before. Imaging services within the polyclinic, Athletes Village, Glasgow 2014 CWG. The aim of the paper is to analyse data on radiological investigations and assess the demand and distribution of workload on imaging services at CWG 2014. Data on radiology investigations at the CWG 2014 was retrieved from the Carestream picture archiving and communication system (PACS) and Pharmasys (CWG official centralised electronic database system) and analysed. Six hundred ninety-seven diagnostic and interventional procedures were performed. Of these 37.9 % were magnetic resonance imaging (MRI) scans, 22 % were diagnostic ultrasound (US) examinations, 33.1 % were radiographs, 4.3 % were computed tomography (CT) scans and 2.7 % were imaging-guided interventional procedures. 88 % of imaging was performed on athletes and the remainder were performed on team officials and workforce. Demand on radiology services gradually picked up through the pre-competition period and peaked half way through the CWG. Radiology played a vital role in the successful provision of medical services at the Glasgow 2014 CWG. High demand on imaging services can be expected at major international sporting events and therefore pre-event planning is vital. Having back-up facilities in case of technical failure should be given due importance when planning radiology services at future CWG events. (orig.)

  16. Data analysis and review of radiology services at Glasgow 2014 Commonwealth Games

    Energy Technology Data Exchange (ETDEWEB)

    Bethapudi, Sarath [County Durham Darlington Foundation NHS Trust, Durham (United Kingdom); Glasgow 2014 Commonwealth Games, Glasgow (United Kingdom); Ritchie, David [Glasgow 2014 Commonwealth Games, Glasgow (United Kingdom); Greater Glasgow and Clyde Hospitals NHS Trust, Western Infirmary, Glasgow (United Kingdom); Bongale, Santosh [Glasgow 2014 Commonwealth Games, Immediate Care Department, Glasgow (United Kingdom); NHS Greater Glasgow and Clyde, Royal Alexandra Hospital, Paisley (United Kingdom); Gordon, Jonny [Glasgow 2014 Commonwealth Games, Glasgow (United Kingdom); NHS Greater Glasgow and Clyde, Glasgow (United Kingdom); MacLean, John [Glasgow 2014 Commonwealth Games, Glasgow (United Kingdom); National Stadium Sports Medicine Centre, Glasgow (United Kingdom); Mendl, Liz [Glasgow 2014 Commonwealth Games, Glasgow (United Kingdom)

    2015-10-15

    Medical services at the Glasgow 2014 Commonwealth Games (CWG) were provided though a purpose-built medical polyclinic, which had a fully equipped radiology department along with other services, set up within the main Games Village. Data analysis of radiology services offered at CWG has not been published before. Imaging services within the polyclinic, Athletes Village, Glasgow 2014 CWG. The aim of the paper is to analyse data on radiological investigations and assess the demand and distribution of workload on imaging services at CWG 2014. Data on radiology investigations at the CWG 2014 was retrieved from the Carestream picture archiving and communication system (PACS) and Pharmasys (CWG official centralised electronic database system) and analysed. Six hundred ninety-seven diagnostic and interventional procedures were performed. Of these 37.9 % were magnetic resonance imaging (MRI) scans, 22 % were diagnostic ultrasound (US) examinations, 33.1 % were radiographs, 4.3 % were computed tomography (CT) scans and 2.7 % were imaging-guided interventional procedures. 88 % of imaging was performed on athletes and the remainder were performed on team officials and workforce. Demand on radiology services gradually picked up through the pre-competition period and peaked half way through the CWG. Radiology played a vital role in the successful provision of medical services at the Glasgow 2014 CWG. High demand on imaging services can be expected at major international sporting events and therefore pre-event planning is vital. Having back-up facilities in case of technical failure should be given due importance when planning radiology services at future CWG events. (orig.)

  17. Cost-benefit analysis for U.S. NRC proposed radiological criteria for decommissioning

    International Nuclear Information System (INIS)

    Meck, R.A.

    1995-01-01

    The U.S. Nuclear Regulatory Commission prepared cost-benefit analyses in support of the proposed regulation on radiological criteria for decommissioning. These analyses have been published in the Draft Generic Environmental Impact Statement (GEIS), NUREG-1496, and in the Draft Regulatory Analysis (RA). The method used was to first list the reasonable regulatory alternatives that could be considered. Second, for each regulatory alternative, we analyzed and compared the costs and the incremental radiological and non-radiological impacts to workers and members of the public. The regulatory alternatives for unrestricted use of a site that were analyzed and compared were: no regulatory change; a uniform risk based on total effective dose equivalent (TEDE); use of 'best' available technology; and returning the level of radioactivity attributable to licensed activity to background levels. The analyses were performed for ten types of reference facilities, and each facility was evaluated at low, medium, and high levels of contamination. The reference facilities included: reactors; various uranium and non-fuel cycle facilities; and independent spent fuel storage installations. Since both the radiological and non-radiological benefits were considered, the benefits of the various alternatives were measured in terms of 'Estimated Mortalities Averted.' Conclusions supported by the analyses were that a risk limit, expressed as a 15 mrem/y dose, is reasonable both as a level for protecting public health and safety and with regard to its cost-benefit effects. Further reductions on a site-specific application of the ALARA principle are also supported in the context of accounting for both the radiological and non-radiological effects in both the short and long terms. Restricted release is also supported when the same level of protection is provided in decommissioning those facilities that cannot reasonably meet the unrestricted release criteria. (J.P.N.)

  18. A joint analysis of determinants and performance consequences of ambidexterity

    OpenAIRE

    Eva M. Pertusa-Ortega; José F. Molina-Azorín

    2018-01-01

    Summary: This paper simultaneously analyzes antecedents and consequences of organizational ambidexterity. Regarding antecedents, the paper examines the influence of internal antecedents (organizational structure) and external antecedents (environmental dynamism). With regard to consequences, the paper analyzes the impact of ambidexterity on firm performance. Moreover, we use two different approaches to ambidexterity (structural and contextual perspectives). The findings show that a hybrid org...

  19. Health effects models for nuclear power plant accident consequence analysis

    International Nuclear Information System (INIS)

    Evans, J.S.; Abrahmson, S.; Bender, M.A.; Boecker, B.B.; Scott, B.R.; Gilbert, E.S.

    1993-10-01

    This report is a revision of NUREG/CR-4214, Rev. 1, Part 1 (1990), Health Effects Models for Nuclear Power Plant Accident Consequence Analysis. This revision has been made to incorporate changes to the Health Effects Models recommended in two addenda to the NUREG/CR-4214, Rev. 1, Part 11, 1989 report. The first of these addenda provided recommended changes to the health effects models for low-LET radiations based on recent reports from UNSCEAR, ICRP and NAS/NRC (BEIR V). The second addendum presented changes needed to incorporate alpha-emitting radionuclides into the accident exposure source term. As in the earlier version of this report, models are provided for early and continuing effects, cancers and thyroid nodules, and genetic effects. Weibull dose-response functions are recommended for evaluating the risks of early and continuing health effects. Three potentially lethal early effects -- the hematopoietic, pulmonary, and gastrointestinal syndromes are considered. Linear and linear-quadratic models are recommended for estimating the risks of seven types of cancer in adults - leukemia, bone, lung, breast, gastrointestinal, thyroid, and ''other''. For most cancers, both incidence and mortality are addressed. Five classes of genetic diseases -- dominant, x-linked, aneuploidy, unbalanced translocations, and multifactorial diseases are also considered. Data are provided that should enable analysts to consider the timing and severity of each type of health risk

  20. Structural consequences of carbon taxes: An input-output analysis

    International Nuclear Information System (INIS)

    Che Yuhu.

    1992-01-01

    A model system is provided for examining for examining the structural consequences of carbon taxes on economic, energy, and environmental issues. The key component is the Iterative Multi-Optimization (IMO) Process model which describes, using an Input-Output (I-O) framework, the feedback between price changes and substitution. The IMO process is designed to assure this feedback process when the input coefficients in an I-O table can be changed while holding the I-O price model. The theoretical problems of convergence to a limit in the iterative process and uniqueness (which requires all IMO processes starting from different initial prices to converge to a unique point for a given level of carbon taxes) are addressed. The empirical analysis also examines the effects of carbon taxes on the US economy as described by a 78 sector I-O model. Findings are compared with those of other models that assess the effects of carbon taxes, and the similarities and differences with them are interpreted in terms of differences in the scope, sectoral detail, time frame, and policy assumptions among the models

  1. Energy sector from 1990 to 2005 - analysis and consequences

    International Nuclear Information System (INIS)

    Granic, G.

    2005-01-01

    The paper analyzes the energy sector in the period from 1990 to 2005. What is shown here through an analysis of political, economic, energy, technological and institutional processes, and based on actual developments and non-developments, the consequences on energy situation to be evolved in the next 15 years, are analyzed. A crucial characteristic of this period is the fact that consumption growth is more distant from the trends in the developed countries and is increasingly approaching ones occurring in developing and undeveloped countries. The other such characteristic is lack of technological progress, which could generate desirable structural changes in energy production and demand. Taking in consideration what has been accomplished so far and what has not been accomplished, we cannot expect in the coming period the changes that could significantly modify the relations in the structure of energy production and demand. Keeping the balance between production and demand will be increasingly difficult, as well as keeping the influence on energy prices which will be growing. In this, it is more than ever indispensable that the state takes up its role.(author)

  2. Health effects estimation code development for accident consequence analysis

    International Nuclear Information System (INIS)

    Togawa, O.; Homma, T.

    1992-01-01

    As part of a computer code system for nuclear reactor accident consequence analysis, two computer codes have been developed for estimating health effects expected to occur following an accident. Health effects models used in the codes are based on the models of NUREG/CR-4214 and are revised for the Japanese population on the basis of the data from the reassessment of the radiation dosimetry and information derived from epidemiological studies on atomic bomb survivors of Hiroshima and Nagasaki. The health effects models include early and continuing effects, late somatic effects and genetic effects. The values of some model parameters are revised for early mortality. The models are modified for predicting late somatic effects such as leukemia and various kinds of cancers. The models for genetic effects are the same as those of NUREG. In order to test the performance of one of these codes, it is applied to the U.S. and Japanese populations. This paper provides descriptions of health effects models used in the two codes and gives comparisons of the mortality risks from each type of cancer for the two populations. (author)

  3. Clinical and radiologic analysis of the pancreatic pseudocyst

    International Nuclear Information System (INIS)

    Lee, Jong Yul; Chung, Bong Jin; Kim, Sung Soo; Park, Sam Kyoon

    1985-01-01

    Pancreatic pseudocyst is encapsulated collections of exudate, blood, and secretions that result from pancreatic necrosis or rupture of ducts and acini, and frequently result in various life threating complications. The barium study of the upper G.I. tract is the most valuable method in diagnosis of the pancreatic pseudocyst. Total 30 cases of surgically proved pancreatic pseudocyst were analyzed. The results were as follows: 1. 56.6% was male, and peak incidence was in the 5th decade. 2. Etiologic factors were blunt abdominal trauma (30%) pancreatitis (23%), and unknown (47%). 3. The most important radiologic findings was stomach displacement(100%), and the others were colon displacement (69%), mass seen in simple abdomen (67%), left kidney displacement (46%), duodental deformity (40%), elevation of diaphragm (37%), pleural effusion (27%), and pancreatic calcification (7%). 4. The most frequent site of the pseudocyst in U.G.I. series was between the greater curvature of the antrum of the stomach and transverse colon (40%). The other sites were near the incisura angularis of the lesser curvature (12%), greater curvature of the antrum (12%), and greater curvature of the body of stomach (4%). 5. The location of the pseudocyst was mainly in the body and tail of the pancreas (90%), only 3 cases (10%) was in the head.

  4. Radiologic analysis of the medical collateral ligament rupture

    International Nuclear Information System (INIS)

    Cho, Chung Che; Lee, Chang Jun; Kim, Kun Sang; Park, Soo Soung

    1979-01-01

    The medical collateral ligament rupture is the most common injury involving the knee joint ligaments. The ruptured medical collateral ligaments of 73 cases with clinical and surgical confirmations were radiologically analyzed. The results were obtained as follows: 1. The most risky age for tearing of the medical collateral ligament was third to fifth decades (50 cases of male and 23 of females). 2. The most common cause of the medical collateral ligament rupture was traffic accident (82.2%). 3. The mean distance of medial knee joint space was 7.9 ± 2.0 mm on the normal side and 13.7 ± 4.2 mm on the affected side. 4. The mean degree of knee joint space was 10.1 ± 2.5 on the normal side and 14.7 ± 3.8 on the affected side. 5. The fibula was the bone fractured most frequently in association with the medial collateral ligament rupture (30.6%).

  5. Analysis of dose distribution in interventionist radiology professionals

    International Nuclear Information System (INIS)

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

    2005-01-01

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

  6. Review and evaluation of the Millstone Unit 3 probabilistic safety study. Containment failure modes, radiological source - terms and offsite consequences

    International Nuclear Information System (INIS)

    Khatib-Rahbar, M.; Pratt, W.; Ludewig, H.

    1985-09-01

    A technical review and evaluation of the Millstone Unit 3 probabilistic safety study has been performed. It was determined that; (1) long-term damage indices (latent fatalities, person-rem, etc.) are dominated by late failure of the containment, (2) short-term damage indices (early fatalities, etc.) are dominated by bypass sequences for internally initiated events, while severe seismic sequences can also contribute significantly to early damage indices. These overall estimates of severe accident risk are extremely low compared with other societal sources of risk. Furthermore, the risks for Millstone-3 are comparable to risks from other nuclear plants at high population sites. Seismically induced accidents dominate the severe accident risks at Millstone-3. Potential mitigative features were shown not to be cost-effective for internal events. Value-impact analysis for seismic events showed that a manually actuated containment spray system might be cost-effective

  7. Radiological Analysis of 40 K, 226 Ra and 232 Th in Fish ...

    African Journals Online (AJOL)

    Radiological analysis was carried out on fish, crustacean and sediment samples collected from both fresh and marine water of river Igbokoda in the coastal area of Ondo State, Nigeria. The activity concentrations of radionuclides were determined using gamma spectrometry method. The means of the annual effective ...

  8. Radiological analysis of materials sampled on the old nuclear test site of In Ekker (Algeria)

    International Nuclear Information System (INIS)

    Chareyron, Bruno

    2010-01-01

    After having recalled the context of the French nuclear test campaign in Algeria between 1961 and 1966, this document reports and comments radiological measurements performed on the site of In Ekker, and also results of analysis performed in laboratory (contamination by cesium 137, americium 241, plutonium); recommendations are given

  9. The radiological consequences of notional accidental releases of radioactivity from fast breeder reactors: sensitivity of the incidence of early effects to the duration

    International Nuclear Information System (INIS)

    Hemming, C.R.; Hallam, J.; Kelly, G.N.

    1979-12-01

    The radiological consequences of a wide range of notional accidental releases from a 1300 MW(e) LMFBR were assessed in a study published in 1977 (NRPB-R53). In that study representative values were in general adopted for each of the important parameters while recognising that in reality they could vary considerably. In this study the sensitivity of the predicted incidence of early effects to the release duration, in so far as it affects the crosswind spread of the activity, is investigated. Two situations are considered; a short release in which the crosswind distribution of the activity is assumed to be Gaussian and a more prolonged release (as modelled in the initial study) in which the crosswind distribution of activity is assumed uniform over a 30 0 sector. For the particular conditions and population distributions considered, the incidence of early effects is greater for the short compared with the more prolonged release. The size of the increase depends upon the radionuclide composition, the magnitude of the release, the distribution of the exposed population, and the prevailing meteorological conditions, but in general the increase is not large. This relatively limited sensitivity indicates that the results obtained in the initial study can be assumed, to a good approximation, to be applicable irrespective of the release duration. (author)

  10. Management of radiological related equipments. Creating the equipment management database and analysis of the repair and maintenance records

    International Nuclear Information System (INIS)

    Eguchi, Megumu; Taguchi, Keiichi; Oota, Takashi; Kajiwara, Hiroki; Ono, Kiyotune; Hagio, Kiyofumi; Uesugi, Ekizo; Kajishima, Tetuo; Ueda, Kenji

    2002-01-01

    In 1997, we established the committee of equipments maintenance and management in our department. We designed the database in order to classify and register all the radiological related equipments using Microsoft Access. The management of conditions and cost of each equipment has become easier, by keeping and recording the database in the equipments management ledger and by filing the history of repairs or maintenances occurred to modalities. We then accounted numbers, cost of repairs and downtimes from the data of the repair and maintenance records for four years, and we reexamined the causal analysis of failures and the contents of the regular maintenance for CT and MRI equipments that had shown the higher numbers of repairs. Consequently, we have found the improvement of registration method of the data and the more economical way to use of the cost of repair. (author)

  11. Multi-criteria analysis to support decision-making process in the event of radiological emergency in tropical climate countries

    International Nuclear Information System (INIS)

    Pereira, Jose F.; Rochedo, Elaine R.R.; Wasserman, Maria A.V.; Silva, Diogo N.G.

    2008-01-01

    Full text: The Multi-criteria Analysis has been widely used in the most diverse areas of the knowledge such as Economy, Transport, Industry, Production, among others. The Multi-criteria Analysis aims to support the decision process, based on the comparison of alternatives, leading to the recommendation of optimized actions in support to decision makers. One of the permanent concerns in the international scenario is the study of the nuclear/radiological consequences of accidents and other events that lead to the contamination of the environment and the exposure of members of the public as a consequence of this contamination. The Multi-criteria Analysis Method is already being used for similar applications in some European countries but it is necessary that the criteria are established taking in account economic, social and climatic aspects that can affect the selection of protective measures applicable to specific regions, and the selection of the different weights to be associated to the different criteria that are to be applied to different social-politic environments. The present work describes the development, already in advanced phase, of a Multi-criteria tool to support the decision making process for the implementation of protective measures to protect the public in situations of radiological accidents, with the degree of flexibility to be easily adapted to the different social, political and climatic regions of Brazil, through the comparison of different options considering a diversity of aspects, such as the efficiency of the measure in the reducing public exposure, the radiation doses that would be received by the workers, the characteristics of the generated wastes, the difficulty of implementation of the measures, as well as the operational costs related to the implementation of the measures. The aim of such analysis is to supply an optimized guidance, under the point of view of radiological protection, adequate for different types of environments that

  12. Analysis and evaluation of the radiological aspects of scoliosis

    International Nuclear Information System (INIS)

    Vargas Gonzalez, Paula

    2012-01-01

    The theme of scoliosis is proposed from the radiological perspective. An extensive literature review is realized, extracting the most relevant information for research. The initiation and evolution of scoliosis has been silent, therefore, to meet this condition has been important to detect it early and opportunely, before that curvatures have progressed and become structured, forcing the surgical treatment. The timely correction of curvatures in the spine has generated significant conditions in the patient's life. The early diagnosis has been fundamental to realize an opportune treatment of orthopedic type. A great variety of congenital and developmental disorders have been evident in the spine. The causes and patterns of the abnormal curvature of the spine have been varied. Precise diagnosis of these alterations is supported on a careful clinical assessment and is aided by imaging explorations, such as conventional radiography, computed tomography, ultrasound and magnetic resonance. Imaging methods to detect scoliosis are mentioned. The measurement procedures of the angle of spine curve are determined. The classification of scoliosis according to King-Lenke are cited to facilitate objective assessment of a disease for examiners, making that the results are presented in shape uniform and comparable possible. The types of scoliosis are explained. The characterization of the deformities of the axis of the spine, quantification and estimation of the degree of skeletal maturity has been the principal objective of the spine radiography. In an radiography has been important to be included all the thoracolumbar spine from C7. The Cobb and Ferguson measurements are used to measure angles, Risser for skeletal maturation, Nas and Moe for vertical rotation. Congenital deformities should be taken into account in radiographs of spine. Each vertebra is examined minutely in search of malformations of fusion, etc., that explain scoliosis. In neurological disorders, to take

  13. Enhanced probabilistic decision analysis for radiological confinement barriers of the International Thermonuclear Experimental Reactor

    International Nuclear Information System (INIS)

    Golinescu, R.P.; Kazimi, M.S.

    1998-01-01

    To ensure a defence-in-depth approach, several radiological confinement barriers surrounding a tokamak plant can be employed. A methodology using probabilistic risk assessment (PRA) techniques is a useful tool for evaluating the performance of each confinement barrier within the context of a limited allowable risk of accidental radioactivity releases. Such a methodology was developed and applied to the confinement strategy for the International Thermonuclear Experimental Reactor (ITER). Accident sequence models were constructed for each of the confinement barriers to evaluate the probabilities of events leading to radioactive releases from the corresponding confinement barrier. The current ITER design requirements set radioactive release and dose limits for individual event sequences grouped in categories by frequency. To limit the plant's overall risk and account for event uncertainties in both frequency and consequence, an analytical form for a limit line is derived here as a complementary cumulative frequency (CCF) of radioactive releases to the environment. By comparing the releases from each confinement barrier against the limit line, a decision can be made about the number of barriers required to comply with the design requirements. The first barrier is the vacuum vessel (VV) and the primary heat transfer systems. The second confinement barrier consists of the cryostat vessel (CV) and the heat transfer system vaults. In case the outer building is needed to act as a third barrier for ITER, a decision model using the multi-attribute utility theory was constructed to help the designer choose the best type of tokamak building. The decision model allows for performing sensitivity analysis on relevant parameters and for design features of new options for the ITER tokamak building. (orig.)

  14. Radiological health effects models for nuclear power plant accident consequence analysis

    International Nuclear Information System (INIS)

    Evans, J.S.; Moeller, D.W.

    1989-01-01

    Improved health effects models have been developed for assessing the early effects, late somatic effects and genetic effects that might result from low-LET radiation exposures to populations following a major accident in a nuclear power plant. All the models have been developed in such a way that the dynamics of population risks can be analyzed. Estimates of life years lost and the duration of illnesses were generated and a framework recommended for summarizing health impacts. Uncertainty is addressed by providing models for upper, central and lower estimates of most effects. The models are believed to be a significant improvement over the models used in the U.S. Nuclear Regulatory Commission's Reactor Safety Study, and they can easily be modified to reflect advances in scientific understanding of the health effects of ionizing radiation

  15. Health effects models for off-site radiological consequence analysis of nuclear reactor accidents

    International Nuclear Information System (INIS)

    Togawa, Orihiko; Homma, Toshimitsu; Matsuzuru, Hideo; Kobayashi, Sadayoshi

    1991-02-01

    A first version of models has been developed for predicting the number of occurrences of health effects induced by radiation exposure in nuclear reactor accidents. The models are based on the health effects models developed originally by Harvard University (NUREG/CR-4214). These models are revised on the basis of the new information on risk estimates by the reassessment of the radiation dosimetry in Hiroshima and Nagasaki. The models deal with the following effects: (1) early effects models for bone marrow, lungs, gastrointestinal tract, central nervous system, thyroid, skin and reproductive organs, using the Weibull function, (2) late somatic effects models including leukemia and cancers of breast, lungs, thyroid, gastrointestinal tract and so forth, on the basis of the information derived from epidemiological studies on the atomic bomb survivors of Hiroshima and Nagasaki, (3) models for late and developmental effects due to exposure in utero. (author)

  16. A joint analysis of determinants and performance consequences of ambidexterity

    Directory of Open Access Journals (Sweden)

    Eva M. Pertusa-Ortega

    2018-04-01

    Full Text Available Summary: This paper simultaneously analyzes antecedents and consequences of organizational ambidexterity. Regarding antecedents, the paper examines the influence of internal antecedents (organizational structure and external antecedents (environmental dynamism. With regard to consequences, the paper analyzes the impact of ambidexterity on firm performance. Moreover, we use two different approaches to ambidexterity (structural and contextual perspectives. The findings show that a hybrid organizational structure, with organic (decentralization and mechanistic characteristics (differentiation and formalization, and environmental dynamism, influence ambidexterity, and there is a positive impact of ambidexterity on firm performance. Keywords: Organizational ambidexterity, Structural approach, Contextual approach, Organizational structure, Environmental dynamism, Firm performance

  17. Nuclear dynamics consequence analysis of SNF disposed in volcanic tuff

    International Nuclear Information System (INIS)

    Sanchez, L.C.; Cochrane, K.; Rath, J.S.; Taylor, L.L.

    1998-05-01

    This paper describes criticality analyses for spent nuclear fuels in a geologic repository. The analyses investigated criticality potential, criticality excursion consequences, and the probability frequency for nuclear criticality. Key findings include: expected number of fissions per excursion range from 10 17 to 10 20 , repeated rate of criticalities range from 3 to 30 per year, and the probability frequency for criticality initiators (based on rough-order-of-magnitude calculations) is 7x10 -7 . Overall results indicate that criticality consequences are a minor contribution to the biological hazards caused by the disposal of spent nuclear material

  18. 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)

  19. Oxygenates in automotive fuels. Consequence analysis - preliminary study

    International Nuclear Information System (INIS)

    Brandberg, Aa.; Saevbark, B.

    1994-01-01

    Oxygenates is used in gasoline due to several reasons. They are added as high-octane components in unleaded gasoline and as agents to reduce the emission of harmful substances. Oxygenates produced from biomass might constitute a coming market for alternative fuels. This preliminary study describes the prerequisites and consequences of such an oxygenate utilization. 39 refs, 9 figs, 5 tabs

  20. An Analysis of the Causes and Consequences of Kidnapping in ...

    African Journals Online (AJOL)

    Thus, the objectives of the study are: to examine the nexus between terrorism and kidnapping; to investigate the mutual reinforcement between corruption and kidnapping; to find out if kidnapping and poverty are correlated; and to examine the consequences of the problem. Using secondary qualitative data, the study found ...

  1. 40 CFR 1400.9 - Access to off-site consequence analysis information by State and local government officials.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 32 2010-07-01 2010-07-01 false Access to off-site consequence... CONSEQUENCE ANALYSIS INFORMATION DISTRIBUTION OF OFF-SITE CONSEQUENCE ANALYSIS INFORMATION Access to Off-Site Consequence Analysis Information by Government Officials. § 1400.9 Access to off-site consequence analysis...

  2. The impact of European research ethics legislation on UK radiology research activity: a bibliometric analysis

    International Nuclear Information System (INIS)

    Johnson, C.A.; Toms, A.P.

    2009-01-01

    Aim: To determine whether there is evidence of a reduction in radiology research activity in the UK following the implementation of the European research ethics legislation, which came in to force in 2001 and has been widely criticised as an impediment to research. Materials and methods: A bibliometric analysis was performed by searching PubMed for all first-author publications from UK departments of 'radiology' or 'medical imaging' between 1995 and 2007. Results were subcategorized into those papers published in the highest cited general radiology journals and by publication type: original research, reviews, and case reports. Results: From 1995 to 2007 the total number of publications rose by 6.5% from 137 to 146 with the increase occurring in non-general radiology journals. Original articles fell from 18 in 1995 to 12 in 2003, but then rose to 24 by 2007 (33% rise). This dip was paralleled by a fall and then recovery in case report publications. The most dramatic change has been in the number of review articles, which has increased more than eightfold from seven in 1995 to 65 in 2007 to become the most common form of publication. Conclusion: The overall number of original scientific articles, published by first-author UK radiologists, has increased slightly over the last 12 years despite a temporary fall associated with the introduction of new research ethics legislation.

  3. Activity-based cost analysis in catheter-based angiography and interventional radiology

    International Nuclear Information System (INIS)

    Rautio, R.; Keski-Nisula, L.; Paakkala, T.

    2003-01-01

    The aim of this study was to analyse the costs of the interventional radiology unit and to identify the cost factors in the different activities of catheter-based angiographies and interventional radiology. In 1999 the number of procedures in the interventional radiological unit at Tampere University Hospital was 2968; 1601 of these were diagnostic angiographies, 526 endovascular and 841 nonvascular interventions. The costs were analysed by using Activity Based Cost (ABC) analysis. The budget of the interventional unit was approximately 1.8 million Euro. Material costs accounted for 67%, personnel costs for 17%, equipment costs for 14% and premises costs for 2% of this. The most expensive products were endografting of aortic aneurysms, with a mean price of 5291 Euro and embolizations of cerebral aneurysms (4472 Euro). Endografts formed 87.3% of the total costs in endografting and Guglielmi detachable coils accounted for 63.3% of the total costs in embolizations. The material costs formed the majority of the costs, especially in the newest and most complicated endovascular treatments. Despite the high cost of angiography equipment, its share of the costs is minor. In our experience ABC system is suitable for analysing costs in interventional radiology. (orig.)

  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. Health effects model for nuclear power plant accident consequence analysis. Part I. Introduction, integration, and summary. Part II. Scientific basis for health effects models

    Energy Technology Data Exchange (ETDEWEB)

    Evans, J.S.; Moeller, D.W.; Cooper, D.W.

    1985-07-01

    Analysis of the radiological health effects of nuclear power plant accidents requires models for predicting early health effects, cancers and benign thyroid nodules, and genetic effects. Since the publication of the Reactor Safety Study, additional information on radiological health effects has become available. This report summarizes the efforts of a program designed to provide revised health effects models for nuclear power plant accident consequence modeling. The new models for early effects address four causes of mortality and nine categories of morbidity. The models for early effects are based upon two parameter Weibull functions. They permit evaluation of the influence of dose protraction and address the issue of variation in radiosensitivity among the population. The piecewise-linear dose-response models used in the Reactor Safety Study to predict cancers and thyroid nodules have been replaced by linear and linear-quadratic models. The new models reflect the most recently reported results of the follow-up of the survivors of the bombings of Hiroshima and Nagasaki and permit analysis of both morbidity and mortality. The new models for genetic effects allow prediction of genetic risks in each of the first five generations after an accident and include information on the relative severity of various classes of genetic effects. The uncertainty in modeloling radiological health risks is addressed by providing central, upper, and lower estimates of risks. An approach is outlined for summarizing the health consequences of nuclear power plant accidents. 298 refs., 9 figs., 49 tabs.

  7. Health effects model for nuclear power plant accident consequence analysis. Part I. Introduction, integration, and summary. Part II. Scientific basis for health effects models

    International Nuclear Information System (INIS)

    Evans, J.S.; Moeller, D.W.; Cooper, D.W.

    1985-07-01

    Analysis of the radiological health effects of nuclear power plant accidents requires models for predicting early health effects, cancers and benign thyroid nodules, and genetic effects. Since the publication of the Reactor Safety Study, additional information on radiological health effects has become available. This report summarizes the efforts of a program designed to provide revised health effects models for nuclear power plant accident consequence modeling. The new models for early effects address four causes of mortality and nine categories of morbidity. The models for early effects are based upon two parameter Weibull functions. They permit evaluation of the influence of dose protraction and address the issue of variation in radiosensitivity among the population. The piecewise-linear dose-response models used in the Reactor Safety Study to predict cancers and thyroid nodules have been replaced by linear and linear-quadratic models. The new models reflect the most recently reported results of the follow-up of the survivors of the bombings of Hiroshima and Nagasaki and permit analysis of both morbidity and mortality. The new models for genetic effects allow prediction of genetic risks in each of the first five generations after an accident and include information on the relative severity of various classes of genetic effects. The uncertainty in modeloling radiological health risks is addressed by providing central, upper, and lower estimates of risks. An approach is outlined for summarizing the health consequences of nuclear power plant accidents. 298 refs., 9 figs., 49 tabs

  8. Evaluating two-dimensional skeletal structure parameters using radiological bone morphometric analysis

    International Nuclear Information System (INIS)

    Asa, Kensuke; Sakurai, Takashi; Kashima, Isamu; Kumasaka, Satsuki

    2005-01-01

    The objectives of this study was to investigate the reliability of two-dimensional (2D) skeletal structure parameters obtained using radiological bone morphometric analysis. The 2D skeletal parameters in the regions of interest (ROIs) were measured on computed radiography (CR) images of first phalanges from racehorses, using radiological bone morphometric analysis. Cancellous bone blocks were made from the phalanges in the same position as the ROI determined on CR images. Three-dimensional (3D) trabecular parameters were measured using micro-computed tomography (μCT). The correlations between the 2D skeletal parameters and 3D trabecular parameters were evaluated in relation to the measured bone strength. The following 2D skeletal structure parameters were correlated with bone strength (r=0.61-0.69): skeletal perimeter (Sk.Pm), skeletal number (Sk.N), skeletal separation (Sk.Sp), skeletal spacing (Sk.Spac), fractal dimension (FD), and skeletal pattern factor (SkPf). The 3D trabecular structure parameters were closely correlated with bone strength (r=0.74-0.86). The 2D skeletal parameters Sk.N, Sk.Pm, FD, SkPf, and Sk.Spac were correlated with the 3D trabecular parameters (r=0.61-0.70). The 2D skeletal parameters obtained using radiological bone morphometric analysis may be useful indicators of trabecular strength. (author)

  9. Improving financial performance by modeling and analysis of radiology procedure scheduling at a large community hospital.

    Science.gov (United States)

    Lu, Lingbo; Li, Jingshan; Gisler, Paula

    2011-06-01

    Radiology tests, such as MRI, CT-scan, X-ray and ultrasound, are cost intensive and insurance pre-approvals are necessary to get reimbursement. In some cases, tests may be denied for payments by insurance companies due to lack of pre-approvals, inaccurate or missing necessary information. This can lead to substantial revenue losses for the hospital. In this paper, we present a simulation study of a centralized scheduling process for outpatient radiology tests at a large community hospital (Central Baptist Hospital in Lexington, Kentucky). Based on analysis of the central scheduling process, a simulation model of information flow in the process has been developed. Using such a model, the root causes of financial losses associated with errors and omissions in this process were identified and analyzed, and their impacts were quantified. In addition, "what-if" analysis was conducted to identify potential process improvement strategies in the form of recommendations to the hospital leadership. Such a model provides a quantitative tool for continuous improvement and process control in radiology outpatient test scheduling process to reduce financial losses associated with process error. This method of analysis is also applicable to other departments in the hospital.

  10. Cost analysis of operating an all-digital radiology department

    International Nuclear Information System (INIS)

    Arenson, R.L.; Soshadri, S.B.; DeSimone, D.; Hiss, S.S.

    1988-01-01

    Using the current film system as a baseline, this study analyzes the cost of digital acquisition, transmission, archiving, and display of all images generated in our department. Two approaches are considered: (1) conventional x-ray films are digitized with a laser scanning film digitizer; (2) images are captured with a direct digital receptor and no film is created. In both approaches, images from digital modalities are acquired directly from the scanners. The cost of equipment and its maintenance, film, supplies, storage space, operations, personnel, and so forth are analyzed for all approaches. The annual cost of operating the film system is $2.5 million. The estimated annual cost is $2.3 million for the first digital approach, $1.8 million for the second. This analysis demonstrates that these digital approaches can be cost-effective, viable alternatives to film-bases systems

  11. Capture and analysis of radiation dose reports for radiology

    International Nuclear Information System (INIS)

    Midgley, S.M.

    2014-01-01

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

  12. Development of an auditable safety analysis in support of a radiological facility classification

    International Nuclear Information System (INIS)

    Kinney, M.D.; Young, B.

    1995-01-01

    In recent years, U.S. Department of Energy (DOE) facilities commonly have been classified as reactor, non-reactor nuclear, or nuclear facilities. Safety analysis documentation was prepared for these facilities, with few exceptions, using the requirements in either DOE Order 5481.1B, Safety Analysis and Review System; or DOE Order 5480.23, Nuclear Safety Analysis Reports. Traditionally, this has been accomplished by development of an extensive Safety Analysis Report (SAR), which identifies hazards, assesses risks of facility operation, describes and analyzes adequacy of measures taken to control hazards, and evaluates potential accidents and their associated risks. This process is complicated by analysis of secondary hazards and adequacy of backup (redundant) systems. The traditional SAR process is advantageous for DOE facilities with appreciable hazards or operational risks. SAR preparation for a low-risk facility or process can be cost-prohibitive and quite challenging because conventional safety analysis protocols may not readily be applied to a low-risk facility. The DOE Office of Environmental Restoration and Waste Management recognized this potential disadvantage and issued an EM limited technical standard, No. 5502-94, Hazard Baseline Documentation. This standard can be used for developing documentation for a facility classified as radiological, including preparation of an auditable (defensible) safety analysis. In support of the radiological facility classification process, the Uranium Mill Tailings Remedial Action (UMTRA) Project has developed an auditable safety analysis document based upon the postulation criteria and hazards analysis techniques defined in DOE Order 5480.23

  13. 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.

  14. 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

  15. Sedation for pediatric radiological procedures: analysis of potential causes of sedation failure and paradoxical reactions

    Energy Technology Data Exchange (ETDEWEB)

    Karian, V.E.; Burrows, P.E.; Connor, L. [Dept. of Radiology, Children' s Hospital, Boston, MA (United States); Zurakowski, D. [Dept. of Biostatistics, Children' s Hospital, Boston, MA (United States); Mason, K.P. [Dept. of Anesthesiology, Children' s Hospital, Boston, MA (United States)

    1999-11-01

    Background. Sedation for diagnostic imaging and interventional radiologic procedures in pediatrics has greatly increased over the past decade. With appropriate patient selection and monitoring, serious adverse effects are infrequent, but failure to sedate and paradoxical reactions do occur. Objective. The purpose of this study was to determine, among patients undergoing sedation for radiologic procedures, the incidence of sedation failure and paradoxical reaction to pentobarbital and to identify potentially correctable causes. Materials and methods. Records of 1665 patients who were sedated in the radiology department from 1 November 1997 to 1 July 1998 were reviewed. Patients failing sedation or experiencing paradoxical reaction were compared with respect to sex, age group, diagnosis, scan type, time of day, NPO status, use of IV contrast and type of sedation agent using the Fisher exact test, Pearson chi-square, analysis of variance (ANOVA), the Student t-test, and logistic regression. Results. Data analysis revealed a sedation failure rate of 1 % and paradoxical reaction rate of 1.2 %. Stepwise multiple logistic regression revealed that the only significant independent multivariate predictor of failure was the need for the administration of a combination of pentobarbital, fentanyl, and midazolam IV. Conclusion. The low rate of sedation failure and paradoxical reactions to pentobarbital was near optimal and probably cannot be improved with the currently available sedatives. (orig.)

  16. Sedation for pediatric radiological procedures: analysis of potential causes of sedation failure and paradoxical reactions

    International Nuclear Information System (INIS)

    Karian, V.E.; Burrows, P.E.; Connor, L.; Zurakowski, D.; Mason, K.P.

    1999-01-01

    Background. Sedation for diagnostic imaging and interventional radiologic procedures in pediatrics has greatly increased over the past decade. With appropriate patient selection and monitoring, serious adverse effects are infrequent, but failure to sedate and paradoxical reactions do occur. Objective. The purpose of this study was to determine, among patients undergoing sedation for radiologic procedures, the incidence of sedation failure and paradoxical reaction to pentobarbital and to identify potentially correctable causes. Materials and methods. Records of 1665 patients who were sedated in the radiology department from 1 November 1997 to 1 July 1998 were reviewed. Patients failing sedation or experiencing paradoxical reaction were compared with respect to sex, age group, diagnosis, scan type, time of day, NPO status, use of IV contrast and type of sedation agent using the Fisher exact test, Pearson chi-square, analysis of variance (ANOVA), the Student t-test, and logistic regression. Results. Data analysis revealed a sedation failure rate of 1 % and paradoxical reaction rate of 1.2 %. Stepwise multiple logistic regression revealed that the only significant independent multivariate predictor of failure was the need for the administration of a combination of pentobarbital, fentanyl, and midazolam IV. Conclusion. The low rate of sedation failure and paradoxical reactions to pentobarbital was near optimal and probably cannot be improved with the currently available sedatives. (orig.)

  17. Application of failure mode and effect analysis in a radiology department.

    Science.gov (United States)

    Thornton, Eavan; Brook, Olga R; Mendiratta-Lala, Mishal; Hallett, Donna T; Kruskal, Jonathan B

    2011-01-01

    With increasing deployment, complexity, and sophistication of equipment and related processes within the clinical imaging environment, system failures are more likely to occur. These failures may have varying effects on the patient, ranging from no harm to devastating harm. Failure mode and effect analysis (FMEA) is a tool that permits the proactive identification of possible failures in complex processes and provides a basis for continuous improvement. This overview of the basic principles and methodology of FMEA provides an explanation of how FMEA can be applied to clinical operations in a radiology department to reduce, predict, or prevent errors. The six sequential steps in the FMEA process are explained, and clinical magnetic resonance imaging services are used as an example for which FMEA is particularly applicable. A modified version of traditional FMEA called Healthcare Failure Mode and Effect Analysis, which was introduced by the U.S. Department of Veterans Affairs National Center for Patient Safety, is briefly reviewed. In conclusion, FMEA is an effective and reliable method to proactively examine complex processes in the radiology department. FMEA can be used to highlight the high-risk subprocesses and allows these to be targeted to minimize the future occurrence of failures, thus improving patient safety and streamlining the efficiency of the radiology department. RSNA, 2010

  18. Cost analysis in interventional radiology-A tool to optimize management costs

    International Nuclear Information System (INIS)

    Clevert, D.-A.; Stickel, M.; Jung, E.M.; Reiser, M.; Rupp, N.

    2007-01-01

    Objective: The objective of the study was to analyze the methods to reduce cost in interventional radiology departments by reorganizing procurement. Materials and methods: All products used in Department of Interventional Radiology were inventoried. An ABC-analysis was completed and A-products (high-value and high turnover products) underwent a XYZ-analysis which predicted demand on the basis of ordering frequency. Then criteria for a procurement strategy for the different material categories were fixed. The net working capital (NWC) was calculated using an interest rate of 8%/year. Results: Total annual material turnover was 353,000 Euro . The value of all A-products determined by the inventory was 260,000 Euro . Changes in the A-product procurement strategy tapped a cost reduction potential of 14,500/year Euro . The resulting total saving was 17,200 Euro . Improved stores management added another 37,500 Euro. The total cost cut of 52,000 Euro is equivalent to 14.7% of annual expenses. Conclusion: A flexible procurement strategy helps to reduce the storage and capital tie-up costs of A-products in interventional radiology without affecting the quality of service provided to patients

  19. An analysis on the satisfaction of radiology students with their major

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jung Hoon; Kang, Se Sik; Kim, Chang Soo [Dept. of Radiological Science, College of Health Sciences, Catholic University of Pusan, Busan (Korea, Republic of)

    2016-06-15

    This study was conducted with a goal to identify the factors that determine radiology students' satisfaction with their major and to provide the basic data for efficient education and career guidance. The result indicated that the students' satisfaction with the professors' roles was high. However, overall, the level of satisfaction with the curriculum was found to be low. In addition, it was analyzed that there was a large gap between recognition and practice of self-directed learning. In the correlation analysis, the professors' roles were also found to be a very important factor. Based on the result, the professors' roles of center(teaching or state examination, students with questions etc.,), it was concluded that improvement of the radiology students' satisfaction with their major would help the students adapt themselves to the major and school successfully and develop a positive character to perform as professionals in the future.

  20. An analysis on the satisfaction of radiology students with their major

    International Nuclear Information System (INIS)

    Kim, Jung Hoon; Kang, Se Sik; Kim, Chang Soo

    2016-01-01

    This study was conducted with a goal to identify the factors that determine radiology students' satisfaction with their major and to provide the basic data for efficient education and career guidance. The result indicated that the students' satisfaction with the professors' roles was high. However, overall, the level of satisfaction with the curriculum was found to be low. In addition, it was analyzed that there was a large gap between recognition and practice of self-directed learning. In the correlation analysis, the professors' roles were also found to be a very important factor. Based on the result, the professors' roles of center(teaching or state examination, students with questions etc.,), it was concluded that improvement of the radiology students' satisfaction with their major would help the students adapt themselves to the major and school successfully and develop a positive character to perform as professionals in the future

  1. Improvement of radiological consequence estimation methodologies for NPP accidents in the ARGOS and RODOS decision support systems through consideration of contaminant physico-chemical forms

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, K.G.; Roos, P. [Technical University of Denmark - DTU (Denmark); Lind, O.C.; Salbu, B. [Norwegian University of Life Sciences/CERAD - NMBU (Norway); Bujan, A.; Duranova, T. [VUJE, Inc. (Slovakia); Ikonomopoulos, A.; Andronopoulos, S. [National Centre for Scientific Research ' Demokritos' (Greece)

    2014-07-01

    The European standard computerized decision support systems RODOS and ARGOS, which are integrated in the operational nuclear emergency preparedness in practically all European countries, as well as in a range of non-European countries, are highly valuable tools for radiological consequence estimation, e.g., in connection with planning and exercising as well as in justification and optimization of intervention strategies. Differences between the Chernobyl and Fukushima accident atmospheric release source terms have demonstrated that differences in release conditions and processes may lead to very different degrees of volatilization of some radionuclides. Also the physico-chemical properties of radionuclides released can depend strongly on the release process. An example from the Chernobyl accident of the significance of this is that strontium particles released in the fire were oxidized and thus generally physico-chemically different from those released during the preceding explosion. This is reflected in the very different environmental mobility of the two groups of particles. The initial elemental matrix characteristics of the contaminants, as well as environmental parameters like pH, determine for instance the particle dissolution time functions, and thus the environmental mobility and potential for uptake in living organisms. As ICRP recommends optimization of intervention according to residual dose, it is crucial to estimate long term dose contributions adequately. In the EURATOM FP7 project PREPARE, an effort is made to integrate physico-chemical forms of contaminants in scenario-specific source term determination, thereby enabling consideration of influences on atmospheric dispersion/deposition, post-deposition migration, and effectiveness of countermeasure implementation. The first step in this context was to investigate, based on available experience, the important physico-chemical properties of radio-contaminants that might potentially be released to the

  2. High-consequence analysis, evaluation, and application of select criteria

    International Nuclear Information System (INIS)

    Gutmanis, I.; Jaksch, J.A.

    1984-01-01

    A number of characteristics distinguish environmental risk from pollution problems. The characteristics make environmental risk problems harder to manage through existing regulatory, legal, and economic institutions. Hence, technologies involving environmental risk impose on society extremely difficult collective decisions. This paper is concerned with the process of reaching social decisions that involve low-probability, high-consequence outcomes. It is divided into five major parts. Part I contains the introduction. Part II reviews the two main classes of criteria that have been proposed for social decisions: approaches based on market mechanisms and their extension, and approaches associated with Rawls and Buchanan, which not only focus on outcomes, but also impose a set of minimal constraints on the process for reaching decisions and social consensus. Part III proposes a set of eight criteria for evaluating social decision processes. In Parts IV and V we investigate applying the criteria to two case studies -- one on nuclear waste disposal and the other on transportation of liquefied natural gas

  3. EDPUFF- a Gaussian dispersion code for consequence analysis

    International Nuclear Information System (INIS)

    Oza, R.B.; Bapat, V.N.; Nair, R.N.; Hukkoo, R.K.; Krishnamoorthy, T.M.

    1995-01-01

    EDPUFF- Equi Distance Puff is a Gaussian dispersion code in FORTRAN language to model atmospheric dispersion of instantaneous or continuous point source releases. It is designed to incorporate the effect of changing meteorological conditions and source release rates on the spatial distribution profiles and its consequences. Effects of variation of parameters like puff spacing, puff packing, averaging schemes are discussed and the choice of the best values for minimum errors and minimum computer CPU time are identified. The code calculates the doses to individual receptors as well as average doses for population zones from internal and external routes over the area of interest. Internal dose computations are made for inhalation and ingestion pathways while the doses from external route consists of cloud doses and doses from surface deposited activity. It computes inhalation and ingestion dose (milk route only) for critical group (1 yr old child). In case of population zones it finds out maximum possible doses in a given area along with the average doses discussed above. Report gives the doses from various pathways for unit release of fixed duration. (author). 7 refs., figs., 7 appendixes

  4. Building Connecticut's clinical biodosimetry laboratory surge capacity to mitigate the health consequences of radiological and nuclear disasters: A collaborative approach between the state biodosimetry laboratory and Connecticut's medical infrastructure

    International Nuclear Information System (INIS)

    Albanese, Joseph; Martens, Kelly; Arnold, Jeffrey L.; Kelley, Katherine; Kristie, Virginia; Forte, Elaine; Schneider, Mark; Dainiak, Nicholas

    2007-01-01

    Biodosimetry, based on the analysis of dicentric chromosomes in circulating mononuclear cells, is considered the 'gold standard' for estimating radiation dose and is used to make informed decisions regarding the medical management of irradiated persons. This paper describes the development of biodosimetry laboratory surge capacity for the health consequences of radiological and nuclear disasters in Connecticut, including: (1) establishment of the Biodosimetry Laboratory for the timely assessment of radiation dosage in biodosimetry specimens; (2) identification of clinical laboratories qualified and willing to process biodosimetry specimens from a large number of victims; (3) training of clinical laboratorians in initial biodosimetry specimen processing; and (4) conducting a functional drill that evaluated the effectiveness of these elements. Descriptive information was obtained from: (1) personal observations; (2) a needs assessment of clinical laboratories in Connecticut; (3) records from a training program of clinical laboratorians in biodosimetry specimen processing that was developed and provided by the Yale New Haven Center for Emergency Preparedness and Disaster Response; and (4) records from a statewide functional drill in biodosimetry specimen processing that was developed and conducted by the State of Connecticut Biodosimetry Laboratory. A needs assessment of clinical laboratories in Connecticut identified 30 of 32 clinical laboratories qualified and willing to perform initial biodosimetry specimen processing. Currently, 79 clinical laboratorians in 19 of these qualified clinical laboratories have been trained in biodosimetry specimen processing. A functional exercise was conducted involving 37 of these trained clinical laboratorians in 18 qualified laboratories as well as the Biodosimetry Laboratory. The average turnaround time for biodosimetry specimen processing in this drill was 199 min. Exercise participants provided feedback which will be used to

  5. Radiological pathways analysis for spent solvents from the boiler chemical cleaning at the Pickering Nuclear Site

    International Nuclear Information System (INIS)

    Garisto, N.C.; Eslami, Z.; Hodgins, S.; Beaman, T.; Von Svoboda, S.; Marczak, J.

    2006-01-01

    Spent solvents are generated as a result of Boiler Chemical Cleanings (BCC) at CANDU reactor sites. These solutions contain small amount of radioactivity from a number of different sources including: Cut tubes - short sections of boiler tubes are infrequently removed from the boilers for a detailed characterization. These tubes are typically only plugged at the tubesheet allowing the primary side deposits to be exposed to BCC solvents. Tube leaks - primary to secondary side leaks also occur infrequently as a result of tube degradation. Radioactivity from the leaking fluid can consequently be deposited in the sludge on the secondary side of the tubes. Diffusion of tritium - during normal operation of the reactor units, tritium slowly diffuses from the heavy water in the primary heat-transfer system to the light-water coolant on the secondary side. Some of this tritium is retained in the secondary side deposits. The Pickering Nuclear Generating Station (PNGS) would like the flexibility to have several options for handling the spent solvent waste and associated rinse water from BCC. To this end, a radiological pathways analysis was undertaken to determine dose consequences associated with each option. Sample results from this study are included in this paper. The pathways analysis is used in this study to calculate dose to hypothetical receptors including individuals such as truck drivers, incinerator workers, residue (ash) handlers, residents who live near the landfill, inadvertent intruders into the landfill after closure and residents who live near the outfall. This dose is compared to a de minimis dose. A de minimis dose or dose rate represents a level of risk, which is generally accepted as being of no significance. Shipments of spent solvents and rinse water with corresponding doses below de minimis can be sent to conventional (i.e., non-radioactive) landfills for incineration and disposal as the radioactive dose associated with them is much less than natural

  6. Numerical analysis of edge effects in side illuminated strip detectors for digital radiology

    CERN Document Server

    Krizaj, D

    2000-01-01

    The influence of edge defects on side illuminated X-ray strip detectors for digital radiology is investigated by numerical device modeling. By assuming positive fixed oxide charges on side and top surfaces simulations have shown strong curvature of the equipotential lines in the edge region. A fraction of the edge generated current surpasses the edge guard-ring junction and is collected by the readout strips. As a consequence, strips cannot be placed close to the edge of the structure and collection efficiency is reduced. An n-on-n instead of a p-on-n strip detector is proposed enabling collection of edge generated carriers by a very narrow guard-ring junction and placement of the readout strip close to the edge without increase of the strip leakage current.

  7. Women authorship in radiology research in France: An analysis of the last three decades.

    Science.gov (United States)

    Pyatigorskaya, N; Di Marco, L

    2017-11-01

    The aim of this study was to evaluate the evolution of women authorship in France and to analyze the recent trends of the evolution of gender differences in French academic radiology. A retrospective bibliometric analysis was performed by searching for articles published in Diagnostic and Interventional Imaging (Diagn Interv Imaging) and in Journal de Radiologie (J Radiol) in Pubmed over the last three decades. For each of these articles, we determined the gender of the first and last author. The specific radiological field of each article was also determined. The proportion of women authors has significantly increased from 12% in 1984 to 34% in 2014 (Pauthorship in Diagnostic and Interventional Imaging has increased over the last years together with the proportion of women first authors. However, the fraction of women last authors is still underrepresented. More women need to become leaders in radiological research to contribute to stimulate women authorship. Copyright © 2017 Éditions françaises de radiologie. Published by Elsevier Masson SAS. All rights reserved.

  8. 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

  9. Fractal analysis in radiological and nuclear medicine perfusion imaging: a systematic review

    Energy Technology Data Exchange (ETDEWEB)

    Michallek, Florian; Dewey, Marc [Humboldt-Universitaet zu Berlin, Freie Universitaet Berlin, Charite - Universitaetsmedizin Berlin, Medical School, Department of Radiology, Berlin (Germany)

    2014-01-15

    To provide an overview of recent research in fractal analysis of tissue perfusion imaging, using standard radiological and nuclear medicine imaging techniques including computed tomography (CT), magnetic resonance imaging (MRI), ultrasound, positron emission tomography (PET) and single-photon emission computed tomography (SPECT) and to discuss implications for different fields of application. A systematic review of fractal analysis for tissue perfusion imaging was performed by searching the databases MEDLINE (via PubMed), EMBASE (via Ovid) and ISI Web of Science. Thirty-seven eligible studies were identified. Fractal analysis was performed on perfusion imaging of tumours, lung, myocardium, kidney, skeletal muscle and cerebral diseases. Clinically, different aspects of tumour perfusion and cerebral diseases were successfully evaluated including detection and classification. In physiological settings, it was shown that perfusion under different conditions and in various organs can be properly described using fractal analysis. Fractal analysis is a suitable method for quantifying heterogeneity from radiological and nuclear medicine perfusion images under a variety of conditions and in different organs. Further research is required to exploit physiologically proven fractal behaviour in the clinical setting. (orig.)

  10. Fractal analysis in radiological and nuclear medicine perfusion imaging: a systematic review

    International Nuclear Information System (INIS)

    Michallek, Florian; Dewey, Marc

    2014-01-01

    To provide an overview of recent research in fractal analysis of tissue perfusion imaging, using standard radiological and nuclear medicine imaging techniques including computed tomography (CT), magnetic resonance imaging (MRI), ultrasound, positron emission tomography (PET) and single-photon emission computed tomography (SPECT) and to discuss implications for different fields of application. A systematic review of fractal analysis for tissue perfusion imaging was performed by searching the databases MEDLINE (via PubMed), EMBASE (via Ovid) and ISI Web of Science. Thirty-seven eligible studies were identified. Fractal analysis was performed on perfusion imaging of tumours, lung, myocardium, kidney, skeletal muscle and cerebral diseases. Clinically, different aspects of tumour perfusion and cerebral diseases were successfully evaluated including detection and classification. In physiological settings, it was shown that perfusion under different conditions and in various organs can be properly described using fractal analysis. Fractal analysis is a suitable method for quantifying heterogeneity from radiological and nuclear medicine perfusion images under a variety of conditions and in different organs. Further research is required to exploit physiologically proven fractal behaviour in the clinical setting. (orig.)

  11. A comparative cost analysis of picture archiving and communications systems (PACS versus conventional radiology in the private sector

    Directory of Open Access Journals (Sweden)

    Indres Moodley

    2015-03-01

    Aim: To undertake an incremental cost analysis of PACS compared with conventional radiology to determine productivity gains, if any, at two private hospitals in Durban. Method: An incremental cost analysis for chest radiographs, computed tomography and magnetic resonance imaging brain scans with and without contrast were performed. The overall incremental cost for PACS in comparison with a conventional radiology site was determined. The net present value was also determined to evaluate the capital budgeting requirements for both systems. Results: The incremental cost of both capital and the radiology information system for installing PACS shows an expected increase. The incremental PACS image cost shows a reduction. Conclusion: The study provides a benchmark for the cost incurred when implementing PACS. It also provides a decision framework for radiology departments that plan to introduce PACS and helps to determine the feasibility of its introduction.

  12. RSL-Nellis Analysis of Radiological Data from the Las Vegas Motor Speedway

    International Nuclear Information System (INIS)

    Wasiolek, Piotr; Okada, Colin

    2009-01-01

    The Department of Energy (DOE) National Nuclear Security Administration (NNSA) is responsible for maintaining national-level radiological emergency response assets and for deploying those assets in the event of a radiological accident or incident. NNSA's emergency response assets include the Aerial Measuring System (AMS) and Search Response Team (SRT) operated by the Remote Sensing Laboratory (RSL) located at Nellis Air Force Base, Las Vegas, Nevada and Andrews Air Force Base in Suitland, Maryland. The AMS mission is to provide a rapid response to radiological emergencies with helicopters and fixed-wing aircraft equipped to detect and measure radioactive material on the ground. The acquired data are stored and used to produce maps of radiation exposure and activity concentration per unit area. AMS also conducts surveys to create radiological baselines of major cities and nuclear facilities throughout the country. The SRT's Crisis Response (CR) mission is to provide scientific, technical, and operational support for NNSA-directed search activities involving radiological search and identification, through both field deployments and home team and reachback support. The AMS radiological mapping and SRT CR emergency response teams from the Remote Sensing Laboratory-Nellis (RSL-N) supported safety and security activities at a NASCAR race at the Las Vegas Motor Speedway (LVMS) on February 27-March 1, 2009. In support of this event, and for proficiency training, these teams carried out aerial and ground surveys of the area. The aerial radiological survey of the LVMS was conducted on February 17, 2009, and the CR ground survey was performed on February 23, 2009. RSL-N operations and appropriate law enforcement agencies selected this area as a suitable location to exercise AMS and CR capabilities for mapping environmental radiation and searching for man-made radioactive sources. The aerial surveys covered approximately 11 square miles. The survey required a 2.5-hour flight

  13. Analysis of a radiological incident and lessons to be learned: a case of industrial radiographic incident in great Britain

    International Nuclear Information System (INIS)

    Croft, J.; Lefaure, Ch.

    2000-01-01

    This note describes a case study to provide feedback analysis and lessons to be learned from a radiological incident. This one occurred in the UK. It has been published in the European ALARA Newsletter no. 2 (January 1997) and has been selected from the IRID database (Ionising Radiation Incident Database) managed by the Health and Safety Executive, National Radiological Protection Board and Environmental Agency. (authors)

  14. Uncertainty analysis in calculations of a road accident consequences

    International Nuclear Information System (INIS)

    Bonnefous, S.; Brenot, J.; Hubert, P.

    1995-01-01

    This paper develops a concrete situation witch is the search for an evacuation distance in case of a road accident implying a chlorine tank. The methodological aspect is how implementing uncertainty analysis in deterministic models with random parameters. The study demonstrates a great dispersion in the results. It allows to establish satisfactory decision rules and a hierarchy on parameters witch is useful to define priorities in the search for information and to improve the treatment of these parameters. (authors). 8 refs., 1 fig., 2 tabs

  15. A discussion on the methodology for calculating radiological and toxicological consequences for the spent nuclear fuel project at the Hanford Site

    International Nuclear Information System (INIS)

    RITTMANN, P.D.

    1999-01-01

    This report contains technical information used to determine accident consequences for the Spent Nuclear Fuel Project safety documents. It does not determine accident consequences or describe specific accident scenarios, but instead provides generic information

  16. 40 CFR 1400.8 - Access to off-site consequence analysis information by Federal government officials.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 32 2010-07-01 2010-07-01 false Access to off-site consequence... MANAGEMENT PROGRAMS UNDER THE CLEAN AIR ACT SECTION 112(r)(7); DISTRIBUTION OF OFF-SITE CONSEQUENCE ANALYSIS INFORMATION DISTRIBUTION OF OFF-SITE CONSEQUENCE ANALYSIS INFORMATION Access to Off-Site Consequence Analysis...

  17. Repeat film analysis and its implications for quality assurance in dental radiology: An institutional case study

    Directory of Open Access Journals (Sweden)

    Shruthi Acharya

    2015-01-01

    Full Text Available Context: The goal of any radiologist is to produce the highest quality diagnostic radiographs, while keeping patient exposure as low as reasonably achievable (ALARA. Aims: The aim of this study was to describe the reasons for radiograph rejections through a repeat film analysis in an Indian dental school. Settings and Design: An observational study conducted in the Department of Oral Medicine and Radiology, Manipal College of Dental Sciences, Manipal. Materials and Methods: During a 6-month study period, a total of 9,495 intra-oral radiographs and 2339 extraoral radiographs taken in the Radiology Department were subjected to repeat film analysis. Statistical Analysis Used: SPSS Version 16. Descriptive analysis used. Results: The results showed that the repeat rates were 7.1% and 5.86% for intraoral and extraoral radiographs, respectively. Among the causes for errors reported, positioning error (38.7% was the most common, followed by improper angulations (26.1%, and improper film placement (11.2% for intra-oral radiographs. The study found that the maximum frequency of repeats among extraoral radiographs was for panoramic radiographs (49% followed by lateral cephalogram (33%, and paranasal sinus view (14%. It was also observed that repeat rate of intraoral radiographs was highest for internees (44.7%, and undergraduate students (28.2%. Conclusions: The study pointed to a need for more targeted interventions to achieve the goal of keeping patient exposure ALARA in a dental school setting.

  18. 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)

  19. Analysis of radiological characteristics distribution in the vertebral bodies of the lumbosacral spine of competitive rowers

    Directory of Open Access Journals (Sweden)

    M.B. Ogurkowska

    2010-09-01

    Full Text Available Unfavorable biomechanical situations, usually related to the performance of a profession and competitive sports practice, promote formation of overloads. This problem may be particularly perceptible among sportsmen that practice strength and stamina sports. The present study deals with rowing. The purpose of this study is to evaluate the degree of degenerative changes of the lumbosacral spine in competitive rowers, on the basis of an analysis of changes in the cancellous structure of vertebral bodies. This has been achieved on the basis of radiological density acquired from a CT test.

  20. Analysis of tables, murals, grids and chassis available for conventional diagnostic radiology

    International Nuclear Information System (INIS)

    Batista, Wilson Otto; Navarro, Marcus Vinicius Teixeira

    2003-01-01

    Tables, bucky, grids, chassis and their combinations produced by several industries have been analysed, verifying and quantifying the attenuation in order to confront the results with the national and international recommendations. The results have shown that some of those tables do not satisfy the national requirements and for that reason increasing the patient dose. As the dose measurements are performed on the table or bucky, the analysis normally is not considered for quality control verifications and have to be considered, as those parts are positioned among the patient and the image receptor (radiological film) influenced the skin dose

  1. Safety aspects in radiology

    International Nuclear Information System (INIS)

    Silva, D.C. da.

    1991-05-01

    The development of a program for the evaluation of the physical installations and operational procedures in diagnostic radiology with respect to radiation-safety is described. In addition, a proposal for the quality analysis of X-ray equipment and film-processing is presented. The purpose is both to ensure quality and safety of the radiology service, as well as to aid in the initial and in-service training of the staff. Interviews with patients, staff practicing radiology at a wide range of levels and the controlling authorities were carried out in the State of Rio de Janeiro in order to investigate the existence and the effective use of personal radioprotection equipment as well as user's and staff's concern for radiation safety. Additionally physical measurements were carried out in University Hospitals in Rio de Janeiro to assess the quality of equipment in day-to-day use. It was found that in the locations which did not have routine maintenance the equipment was generally in a poor state which lead to a high incidence of repetition of examinations and the consequent financial loss. (author)

  2. Film reject analysis and image quality in diagnostic Radiology Department of a Teaching hospital in Ghana

    Directory of Open Access Journals (Sweden)

    J. Owusu-Banahene

    2014-10-01

    Full Text Available Patients usually undergo repeated X-ray examinations after their initial X-ray radiographs are rejected due to poor image quality. This subjects the patients to an excess radiation exposure and extra cost and necessitates the need to investigate the causes of reject. The use of reject analysis as part of the overall quality assurance programs in clinical radiography and radiology services is vital in the evaluation of image quality of a well-established practice. It is shown that, in spite of good quality control maintained by the Radiology Department of a Teaching hospital in Ghana, reject analysis performed on a number of radiographic films developed indicated 14.1% reject rate against 85.9% accepted films. The highest reject rate was 57.1 ± 0.7% which occurs in cervical spine and the lowest was7.7 ± 0.5% for lumbar spine. The major factors contributing to film rejection were found to be over exposure and patient positioning in cervical spine examinations. The most frequent examination was chest X-ray which accounts for about 42.2% of the total examinations. The results show low reject rates by considering the factors for radiographic rejection analysis in relation to both equipment functionality and film development in the facility.

  3. An analysis of radiological research publications in high impact general medical journals between 1996 and 2010

    International Nuclear Information System (INIS)

    Ku, You Jin; Yoon, Dae Young; Yun, Eun Joo; Baek, Sora; Lim, Kyoung Ja; Seo, Young Lan; Choi, Chul Soon; Bae, Sang Hoon

    2013-01-01

    Highlights: ► Radiologists published only 0.2% of articles in five general medical journals. ► Most original articles from radiologists were funded and were prospective studies. ► Radiology researchers from only 11 countries published at least one original article. -- Abstract: Objective: To evaluate scientific papers published by radiologists in high impact general medical journals between 1996 and 2010. Methods: A MEDLINE search was performed in five high impact general medical journals (AIM, BMJ, JAMA, Lancet, and NEJM) for all articles of which a radiologist was the first author between 1996 and 2010. The following information was abstracted from the original articles: radiological subspecialty, imaging technique used, type of research, sample size, study design, statistical analysis, study outcome, declared funding, number of authors, collaboration, and country of the first author. Results: Of 216 (0.19%) articles were published by radiologists in five general medical journals between 1996 and 2010, 83 were original articles. Fifteen (18.1%) original articles were concerned with the field of vascular/interventional radiology, 24 (28.9%) used combined imaging techniques, 76 (91.6%) were clinical research, 63 (75.9%) had a sample size of >50, 65 (78.3%) were prospective, 78 (94.0%) performed statistical analysis, 83 (100%) showed positive study outcomes, 57 (68.7%) were funded, 49 (59.0%) had from four to seven authors, and 79 (95.2%) were collaborative studies. Conclusions: A very small number (0.19%) in five high impact general medical journals was published by radiologists between 1996 and 2010

  4. The application of cost-benefit analysis to the radiological protection of the public

    International Nuclear Information System (INIS)

    1980-03-01

    The subject of this document is the quantification of the potential harm caused to the general public by ionising radiation in normal operating circumstances. The object is to enable the health detriment from a practice involving exposure to ionising radiation to be directly compared with the costs of keeping the ensuing doses as low as reasonably achievable. Chapter headings include: development of radiological protection criteria; principles underlying the valuation of harm from radiation exposure; risk evaluation approach to costing of detriment; monetary valuations; distribution of costs and risk in time. Appendices cover the following: cost benefit analysis (principles); recommendations of ICRP on the use of cost benefit analysis; life valuation studies (review); application of cost benefit analysis to the value of the man sievert. (U.K.)

  5. Methodology for evaluating radiological consequences of the management of very low-level solide waste arising from decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Smith, G.M.; Hemming, C.R.; Clark, J.M.; Chapuis, A.M.; Garbay, H.

    1985-01-01

    In this report a methodology is described, and illustrated by examples, for the evaluation of individual doses and collective dose commitments arising as a result of various management modes for very low-level solid wastes arising from the decommissioning of nuclear power plants. Estimates have been made of the masses of materials activated and contaminated to within three concentration limits, 0.37, 3.7 and 37 Bq g-1, at three times after reactor shutdown, 5 y, 25 y and 100 y. The disposal options considered are shallow land burial, at a municipal landfill site or at the reactor site, and disposal on the seabed in coastal waters or the deep ocean. It is assumed that there is no special treatment to reduce or eliminate the potential radiological hazard. Consideration has also been given to the radiological impact of recycling of contaminated steel. The radiological impacts of all the management options for the wastes considered were found to be small. It may therefore be acceptable to allow such very low-level wastes to be disposal of without special restrictions provided that the level and type of activity of the wastes can be verified. In addition the health detriment cost associated with all the management options is small, so it is likely that other factors such as transport and engineering costs will be more important in final decisions about the management of these wastes

  6. An analysis of radiological research publications in high impact general medical journals between 1996 and 2010.

    Science.gov (United States)

    Ku, You Jin; Yoon, Dae Young; Yun, Eun Joo; Baek, Sora; Lim, Kyoung Ja; Seo, Young Lan; Choi, Chul Soon; Bae, Sang Hoon

    2013-06-01

    To evaluate scientific papers published by radiologists in high impact general medical journals between 1996 and 2010. A MEDLINE search was performed in five high impact general medical journals (AIM, BMJ, JAMA, Lancet, and NEJM) for all articles of which a radiologist was the first author between 1996 and 2010. The following information was abstracted from the original articles: radiological subspecialty, imaging technique used, type of research, sample size, study design, statistical analysis, study outcome, declared funding, number of authors, collaboration, and country of the first author. Of 216 (0.19%) articles were published by radiologists in five general medical journals between 1996 and 2010, 83 were original articles. Fifteen (18.1%) original articles were concerned with the field of vascular/interventional radiology, 24 (28.9%) used combined imaging techniques, 76 (91.6%) were clinical research, 63 (75.9%) had a sample size of >50, 65 (78.3%) were prospective, 78 (94.0%) performed statistical analysis, 83 (100%) showed positive study outcomes, 57 (68.7%) were funded, 49 (59.0%) had from four to seven authors, and 79 (95.2%) were collaborative studies. A very small number (0.19%) in five high impact general medical journals was published by radiologists between 1996 and 2010. Copyright © 2013 Elsevier Ireland Ltd. All rights reserved.

  7. Neutronic Analysis and Radiological Safety of RSG-GAS Reactor on 300 Grams Uranium Silicide Core

    International Nuclear Information System (INIS)

    Pande Made Udiyani; Lily Suparlina; Rokhmadi

    2007-01-01

    As starting of usage silicide U 250 g fuel element in the core of RSG-GAS and will be continued with usage of silicide U 300 g fuel element, hence done beforehand neutronic analyse and radiological safety of RSG-GAS. Calculation done by ORIGEN2.1 code to calculate source term, and also by PC-COSYMA code to calculate radiological safety of radioactive dispersion from RSG-GAS. Calculation of radioactive dispersion done at condition of reactor is postulated be happened an accident of LOCA causing one fuel element to melt. Neutronic analysis indicate that silicide U 250 g full core shall to be operated beforehand during 625 MWD before converted to silicide U 300 g core. During operation of transition core with mixture of silicide U 250 g and 300 g, all parameter fulfill criterion of safety Designed Balance core of silicide U 300 g will be reached at the time of fifth full core. Result of calculation indicate that through mixture core of silicide U 250 and 300 g proposed can form silicide U 300 g balance core of reactor RSG-GAS safely. Calculation of radiology safety by deterministic for silicide U 300 g balance core, and accident postulation which is equal to core of silicide U 250 g yield output in the form of radiation activity (radionuclide concentration in the air and deposition on the ground), radiation dose (collective and individual), radiation effect (short- and long-range), which accepted by society in each perceived sector. Result of calculation indicated that dose accepted by society is not pass permitted boundary for public society if happened accident. (author)

  8. College Alcohol Beliefs and Drinking Consequences: A Multiple Mediation Analysis of Norms, Expectancies, and Willingness to Experience Drinking Consequences

    Science.gov (United States)

    Osberg, Timothy M.; Boyer, Amber

    2018-01-01

    Objective: We explored the potential mediating role of willingness to experience drinking consequences and other traditional alcohol outcome predictors (descriptive norms, injunctive norms, positive alcohol expectancies) in explaining the association between college alcohol beliefs1 (CABs) and the actual experience of drinking consequences among…

  9. Environmental decision support system on base of geoinformational technologies for the analysis of nuclear accident consequences

    International Nuclear Information System (INIS)

    Haas, T.C.; Maigan, M.; Arutyunyan, R.V.; Bolshov, L.A.; Demianov, V.V.

    1996-01-01

    The report deals with description of the concept and prototype of environmental decision support system (EDSS) for the analysis of late off-site consequences of severe nuclear accidents and analysis, processing and presentation of spatially distributed radioecological data. General description of the available software, use of modem achievements of geostatistics and stochastic simulations for the analysis of spatial data are presented and discussed

  10. Clinical and radiological comparison of tuberculous and pyogenic spondylitis. An analysis of 49 operated cases

    International Nuclear Information System (INIS)

    Dzelzite, S.; Maurins, G.

    1998-01-01

    Objective: To perform retrospective analysis of 49 operated patients with histologically proven spondylodiscitis of tbc and pyogenic origin. Patient histories, laboratory tests and radiographic findings were statistically compared between two groups. We estimated that in 16 cases (32.6%) origin of spondylodiscitis was tbc and 33 cases (67.4%) origin was pyogenic. All cases of tbc spondylitis (except one drug resistant tbc form) were with previously proved tbc diagnosis of different localisation. Radiological findings for the tbc cases were more than two-vertebra involvement and deformation of vertebral column axis. Pyogenic spondylodiscitis (33 cases) were derived from or after - 1. lumbal discectomies (7 cases), 2. operation on retroperitoneal cavity (6 cases) including 3 cases after prothesation of abdominal aorta, 3. closed spine trauma (4 cases), 4. hematogenic dissemination of pyogenic infection from different localisation - kidney, lung, sinuses (8 cases). In 8 cases we did not estimate potential cause of spondylodiscitis. Conclusion: A definite diagnosis of spondylodiscitis was established by means of biopsy, histological evidence and bacterial culture. There are not specific radiological findings to differentiate tbc spondylodiscitis from pyogenic spondylodiscitis. (Full text)

  11. Cost analysis of radiological interventional procedures and reimbursement within a clinic

    International Nuclear Information System (INIS)

    Strotzer, M.; Voelk, M.; Lenhart, M.; Fruend, R.; Feuerbach, S.

    2002-01-01

    Purpose: Analysis of costs for vascular radiological interventions on a per patient basis and comparison with reimbursement based on GOAe(Gebuehrenordnung fuer Aerzte) and DKG-NT (Deutsche Krankenhausgesellschaft-Nebenkostentarif). Material and Methods: The ten procedures most frequently performed within 12 months were evaluated. Personnel costs were derived from precise costs per hour and estimated procedure time for each intervention. Costs for medical devices were included. Reimbursement based on GOAewas calculated using the official conversion factor of 0.114 DM for each specific relative value unit and a multiplication factor of 1.0. The corresponding conversion factor for DKG-NT, determined by the DKG, was 0.168 DM. Results: A total of 832 interventional procedures were included. Marked differences between calculated costs and reimbursement rates were found. Regarding the ten most frequently performed procedures, there was a deficit of 1.06 million DM according GOAedata (factor 1.0) and 0.787 million DM according DKG-NT. The percentage of reimbursement was only 34.2 (GOAe; factor 1.0) and 51.3 (DKG-NT), respectively. Conclusion: Reimbursement of radiological interventional procedures based on GOAeand DKG-NT data is of limited value for economic controlling purposes within a hospital. (orig.) [de

  12. Overview on measures concerning the radiation exposure reduction following events with serious radiological consequences (catalogue of measures) Pt. 2. Background information, theory and examples of use

    International Nuclear Information System (INIS)

    Genkel, Simone; Schnadt, Horst

    2010-01-01

    The report edited by the German Federal Ministry for the Environment, Nature Conservation and Nuclear Safety includes the following chapters: Summary of materials: international nuclear and radiological event scale (INES), nuclear power plants in Europe, significance of the reference nuclide I-131, emergency protection measures, radiation protection measures, contaminated surface waters, contaminated matter disposal, prevention of radiation exposure by inhalation, decision making concerning agriculture and food, radiation protection during disposal procedures. Theoretical fundamentals: decontamination, dose rate, contaminated soils, inhalation dose, contaminated articles, contaminated surface waters, contaminated skin, contamination by ingestion, conversion factors, calculation procedures for appropriate measures. Examples for use of the catalogue of measures.

  13. Analysis of data related to the update of diagnosis reference levels in radiology and nuclear medicine. Assessment 2009-2010

    International Nuclear Information System (INIS)

    Roch, Patrice; Celier, David

    2012-10-01

    This report presents and comments the results of the analysis of 'patient' dosimetric data which radiology and nuclear medicine establishments had to transmit to the IRSN. The first part concerns conventional radiology and the analysis is made from a general point of view, and then by examination type (in the case of adults and of children). A synthesis of results since 2004 is proposed in terms of transmitted data, of data representativeness, of influence of detection technology on the delivered dose, of evolution of diagnosis reference level. With the same approach, the next parts address scanography examinations and nuclear medicine

  14. SisRadiologia: a new software tool for analysis of radiological accidents and incidents in industrial radiography

    International Nuclear Information System (INIS)

    Lima, Camila M. Araujo; Silva, Francisco C.A. da; Araujo, Rilton A.

    2013-01-01

    According to the International Atomic Energy Agency (IAEA), many efforts have been made by Member states, aiming a better control of radioactive sources. Accidents mostly happened in practices named as high radiological risk and classified by IAEA in categories 1 and 2, being highlighted those related to radiotherapy, large irradiators and industrial radiography. Worldwide, more than 40 radiological accidents have been recorded in the industrial radiography. Worldwide, more than 40 radiological accidents have been recorded in the industrial radiography area, involving 37 workers, 110 members of the public and 12 fatalities. Records display 5 severe radiological accidents in industrial radiography activities in Brazil, in which 7 workers and 19 members of the public were involved. Such events led to hands and fingers radiodermatitis, but to no death occurrence. The purpose of this study is to present a computational program that allows the data acquisition and recording in the company, in such a way to ease a further detailed analysis of radiological event, besides providing the learning cornerstones aiming the avoidance of future occurrences. After one year of the 'Industrial SisRadiologia' computational program application - and mostly based upon the workshop about Analysis and Dose Calculation of Radiological Accidents in Industrial Radiography (Workshop sobre Analise e Calculo de dose de acidentes Radiologicos em Radiografia Industrial - IRD 2012), in which several Radiation Protection officers took part - it can be concluded that the computational program is a powerful tool to data acquisition, as well as, to accidents and incidents events recording and surveying in Industrial Radiography. The program proved to be efficient in the report elaboration to the Brazilian Regulatory Authority, and very useful in workers training to fix the lessons learned from radiological events.

  15. Radioactive waste management complex low-level waste radiological composite analysis

    Energy Technology Data Exchange (ETDEWEB)

    McCarthy, J.M.; Becker, B.H.; Magnuson, S.O.; Keck, K.N.; Honeycutt, T.K.

    1998-05-01

    The composite analysis estimates the projected cumulative impacts to future members of the public from the disposal of low-level radioactive waste (LLW) at the Idaho National Engineering and Environmental Laboratory (INEEL) Radioactive Waste Management Complex (RWMC) and all other sources of radioactive contamination at the INEEL that could interact with the LLW disposal facility to affect the radiological dose. Based upon the composite analysis evaluation, waste buried in the Subsurface Disposal Area (SDA) at the RWMC is the only source at the INEEL that will significantly interact with the LLW facility. The source term used in the composite analysis consists of all historical SDA subsurface disposals of radionuclides as well as the authorized LLW subsurface disposal inventory and projected LLW subsurface disposal inventory. Exposure scenarios evaluated in the composite analysis include all the all-pathways and groundwater protection scenarios. The projected dose of 58 mrem/yr exceeds the composite analysis guidance dose constraint of 30 mrem/yr; therefore, an options analysis was conducted to determine the feasibility of reducing the projected annual dose. Three options for creating such a reduction were considered: (1) lowering infiltration of precipitation through the waste by providing a better cover, (2) maintaining control over the RWMC and portions of the INEEL indefinitely, and (3) extending the period of institutional control beyond the 100 years assumed in the composite analysis. Of the three options investigated, maintaining control over the RWMC and a small part of the present INEEL appears to be feasible and cost effective.

  16. Radioactive waste management complex low-level waste radiological composite analysis

    International Nuclear Information System (INIS)

    McCarthy, J.M.; Becker, B.H.; Magnuson, S.O.; Keck, K.N.; Honeycutt, T.K.

    1998-05-01

    The composite analysis estimates the projected cumulative impacts to future members of the public from the disposal of low-level radioactive waste (LLW) at the Idaho National Engineering and Environmental Laboratory (INEEL) Radioactive Waste Management Complex (RWMC) and all other sources of radioactive contamination at the INEEL that could interact with the LLW disposal facility to affect the radiological dose. Based upon the composite analysis evaluation, waste buried in the Subsurface Disposal Area (SDA) at the RWMC is the only source at the INEEL that will significantly interact with the LLW facility. The source term used in the composite analysis consists of all historical SDA subsurface disposals of radionuclides as well as the authorized LLW subsurface disposal inventory and projected LLW subsurface disposal inventory. Exposure scenarios evaluated in the composite analysis include all the all-pathways and groundwater protection scenarios. The projected dose of 58 mrem/yr exceeds the composite analysis guidance dose constraint of 30 mrem/yr; therefore, an options analysis was conducted to determine the feasibility of reducing the projected annual dose. Three options for creating such a reduction were considered: (1) lowering infiltration of precipitation through the waste by providing a better cover, (2) maintaining control over the RWMC and portions of the INEEL indefinitely, and (3) extending the period of institutional control beyond the 100 years assumed in the composite analysis. Of the three options investigated, maintaining control over the RWMC and a small part of the present INEEL appears to be feasible and cost effective

  17. GRDC. A Collaborative Framework for Radiological Background and Contextual Data Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Quiter, Brian J. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Ramakrishnan, Lavanya [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Bandstra, Mark S. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

    2015-12-01

    The Radiation Mobile Analysis Platform (RadMAP) is unique in its capability to collect both high quality radiological data from both gamma-ray detectors and fast neutron detectors and a broad array of contextual data that includes positioning and stance data, high-resolution 3D radiological data from weather sensors, LiDAR, and visual and hyperspectral cameras. The datasets obtained from RadMAP are both voluminous and complex and require analyses from highly diverse communities within both the national laboratory and academic communities. Maintaining a high level of transparency will enable analysis products to further enrich the RadMAP dataset. It is in this spirit of open and collaborative data that the RadMAP team proposed to collect, calibrate, and make available online data from the RadMAP system. The Berkeley Data Cloud (BDC) is a cloud-based data management framework that enables web-based data browsing visualization, and connects curated datasets to custom workflows such that analysis products can be managed and disseminated while maintaining user access rights. BDC enables cloud-based analyses of large datasets in a manner that simulates real-time data collection, such that BDC can be used to test algorithm performance on real and source-injected datasets. Using the BDC framework, a subset of the RadMAP datasets have been disseminated via the Gamma Ray Data Cloud (GRDC) that is hosted through the National Energy Research Science Computing (NERSC) Center, enabling data access to over 40 users at 10 institutions.

  18. Analysis of data relative to the update of diagnosis reference levels in radiology and nuclear medicine. Situation 2004-2006

    International Nuclear Information System (INIS)

    2008-01-01

    This report presents the results of the analysis of patients dosimetry data the radiology and nuclear medicine institutions have to transmit yearly to I.R.S.N. in application of the 12. february decree disposal relative to the diagnosis reference levels in radiology and nuclear medicine. The analysed dosimetry data concern the evaluations realised between the date of decree publication, the 16. march 2004 and 31. december 2006. The so considered results have to allow to the Nuclear Safety Authority to define the evolution needs of the regulation. Particularly, the analysis of delivered doses in radiology and the activities given in nuclear medicine lead to propositions on the possible update of reference values of some examination types. (N.C.)

  19. IAEA Perspectives on Radiological Characterisation

    International Nuclear Information System (INIS)

    O'Sullivan, Patrick; Ljubenov, Vladan

    2012-01-01

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

  20. 40 CFR 1400.3 - Public access to paper copies of off-site consequence analysis information.

    Science.gov (United States)

    2010-07-01

    ...-site consequence analysis information. 1400.3 Section 1400.3 Protection of Environment ENVIRONMENTAL... PROGRAMS UNDER THE CLEAN AIR ACT SECTION 112(r)(7); DISTRIBUTION OF OFF-SITE CONSEQUENCE ANALYSIS INFORMATION DISTRIBUTION OF OFF-SITE CONSEQUENCE ANALYSIS INFORMATION Public Access § 1400.3 Public access to...

  1. Geostatistical methods for radiological evaluation and risk analysis of contaminated premises

    International Nuclear Information System (INIS)

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

    2009-01-01

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

  2. Cost benefit analysis of the radiological shielding of medical cyclotrons using a genetic algorithm

    International Nuclear Information System (INIS)

    Mukherjee, Bhaskar

    2001-01-01

    Adequate radiation shielding is vital to the safe operation of modern commercial medical cyclotrons producing large yields of short-lived radioisotopes. The radiological shielding constitutes a significant capital investment for any new cyclotron-based radioisotope production facility; hence, the shielding design requires an accurate cost-benefit analysis often based on a complex multi-variant optimization technique. This paper demonstrates the application of a Genetic Algorithm (GA) for the optimum design of the high yield target cave of a Medical Cyclotron radioisotope production facility based in Sydney, Australia. The GA is a novel optimization technique that mimics the Darwinian Evolution paradigm and is ideally suited to search for global optima in a large multi-dimensional solution space

  3. Radiological accidents: analysis of the information disseminated by media and public acceptance of nuclear technology

    International Nuclear Information System (INIS)

    Delgado, Jose Ubiratan; Tauhata, Luiz; Garcia, Marcia Maria

    1995-01-01

    A methodology to treat quantitatively information by Media concerning a nuclear or a radiological accident is presented. It allows us to classify information according to the amount, importance and way of showing, into one indicator, named Information Equivalent. This establishes a procedure for analysis of released information and includes: number of head-lines, illustrations, printed lines, editorials, authorities quoted and so on. Interpretation becomes easier when the evolution and statistical trend of this indicator is observed. The application to evaluate the dissemination of the accident which took place in 1987 in Goiania, Brazil, was satisfactory and allowed us to purpose a model. This will aid the planning, the decision making process and it will improve relationships between technical staff and media during the emergency. (author). 5 refs., 4 figs., 3 tabs

  4. Indian Point Nuclear Power Station: verification analysis of County Radiological Emergency-Response Plans

    International Nuclear Information System (INIS)

    Nagle, J.; Whitfield, R.

    1983-05-01

    This report was developed as a management tool for use by the Federal Emergency Management Agency (FEMA) Region II staff. The analysis summarized in this report was undertaken to verify the extent to which procedures, training programs, and resources set forth in the County Radiological Emergency Response Plans (CRERPs) for Orange, Putnam, and Westchester counties in New York had been realized prior to the March 9, 1983, exercise of the Indian Point Nuclear Power Station near Buchanan, New York. To this end, a telephone survey of county emergency response organizations was conducted between January 19 and February 22, 1983. This report presents the results of responses obtained from this survey of county emergency response organizations

  5. The novel application of Benford's second order analysis for monitoring radiation output in interventional radiology.

    Science.gov (United States)

    Cournane, S; Sheehy, N; Cooke, J

    2014-06-01

    Benford's law is an empirical observation which predicts the expected frequency of digits in naturally occurring datasets spanning multiple orders of magnitude, with the law having been most successfully applied as an audit tool in accountancy. This study investigated the sensitivity of the technique in identifying system output changes using simulated changes in interventional radiology Dose-Area-Product (DAP) data, with any deviations from Benford's distribution identified using z-statistics. The radiation output for interventional radiology X-ray equipment is monitored annually during quality control testing; however, for a considerable portion of the year an increased output of the system, potentially caused by engineering adjustments or spontaneous system faults may go unnoticed, leading to a potential increase in the radiation dose to patients. In normal operation recorded examination radiation outputs vary over multiple orders of magnitude rendering the application of normal statistics ineffective for detecting systematic changes in the output. In this work, the annual DAP datasets complied with Benford's first order law for first, second and combinations of the first and second digits. Further, a continuous 'rolling' second order technique was devised for trending simulated changes over shorter timescales. This distribution analysis, the first employment of the method for radiation output trending, detected significant changes simulated on the original data, proving the technique useful in this case. The potential is demonstrated for implementation of this novel analysis for monitoring and identifying change in suitable datasets for the purpose of system process control. Copyright © 2013 Associazione Italiana di Fisica Medica. Published by Elsevier Ltd. All rights reserved.

  6. Analysis of skull asymmetry in different historical periods using radiological examinations

    International Nuclear Information System (INIS)

    Gawlikowska, A.; Czerwinski, F.; Dzieciolowska, E.; Miklaszewska, D.; Adamiec, E.; Szczurowski, J.

    2007-01-01

    Asymmetry is a very common phenomenon in nature. Occurrence of asymmetry and knowledge of correct structure, especially a range of variability which is not a pathology but only an individual variation, are the basis for interpretation of results of radiological examination of the skulls both in research work and in diagnostic examinations, which are widely performed in modern medicine. There are many methods of estimation of the asymmetry. The aim of this study was to estimate the symmetry of skulls from selected historic populations. The studied material consisted of two skull populations - contemporary consisting of 82 skulls and medieval - 77 skulls from Grodek. X-rays in P-A and skull-base projections were performed. The images were scanned and calibrated by means of MicroStation 95 Academic Edition software. Using tools for measurement of vector elements, distances between selected bilateral points of the skull were taken. All data were analyzed statistically. Asymmetry was observed in the skulls of both populations. Some diameters were higher on the left side, some on the right side. High levels of asymmetry index in the superior facial part and in the posterior part of the skull base were observed. The levels of the asymmetry indexes in both groups were similar. Radiological pictures in two projections should be taken for correct analysis of the skull asymmetry. The examination of the asymmetry of the landmarks should be based on the analysis of diameters from two different points of reference. The human skull does not demonstrate a clear domination of one side. The largest variations were observed in the shape and localization of the foramina of the skull . It is associated with the differences of the position of the neurovascular elements which pass through these foramina. (author)

  7. Toxic release consequence analysis tool (TORCAT) for inherently safer design plant

    International Nuclear Information System (INIS)

    Shariff, Azmi Mohd; Zaini, Dzulkarnain

    2010-01-01

    Many major accidents due to toxic release in the past have caused many fatalities such as the tragedy of MIC release in Bhopal, India (1984). One of the approaches is to use inherently safer design technique that utilizes inherent safety principle to eliminate or minimize accidents rather than to control the hazard. This technique is best implemented in preliminary design stage where the consequence of toxic release can be evaluated and necessary design improvements can be implemented to eliminate or minimize the accidents to as low as reasonably practicable (ALARP) without resorting to costly protective system. However, currently there is no commercial tool available that has such capability. This paper reports on the preliminary findings on the development of a prototype tool for consequence analysis and design improvement via inherent safety principle by utilizing an integrated process design simulator with toxic release consequence analysis model. The consequence analysis based on the worst-case scenarios during process flowsheeting stage were conducted as case studies. The preliminary finding shows that toxic release consequences analysis tool (TORCAT) has capability to eliminate or minimize the potential toxic release accidents by adopting the inherent safety principle early in preliminary design stage.

  8. Bibliometric Analysis of Manuscript Characteristics That Influence Citations: A Comparison of Six Major Radiology Journals.

    Science.gov (United States)

    Shekhani, Haris Naseem; Shariff, Shoaib; Bhulani, Nizar; Khosa, Faisal; Hanna, Tarek Noel

    2017-12-01

    The objective of our study was to investigate radiology manuscript characteristics that influence citation rate, capturing features of manuscript construction that are discrete from study design. Consecutive articles published from January 2004 to June 2004 were collected from the six major radiology journals with the highest impact factors: Radiology (impact factor, 5.076), Investigative Radiology (2.320), American Journal of Neuroradiology (AJNR) (2.384), RadioGraphics (2.494), European Radiology (2.364), and American Journal of Roentgenology (2.406). The citation count for these articles was retrieved from the Web of Science, and 29 article characteristics were tabulated manually. A point-biserial correlation, Spearman rank-order correlation, and multiple regression model were performed to predict citation number from the collected variables. A total of 703 articles-211 published in Radiology, 48 in Investigative Radiology, 106 in AJNR, 52 in RadioGraphics, 129 in European Radiology, and 157 in AJR-were evaluated. Punctuation was included in the title in 55% of the articles and had the highest statistically significant positive correlation to citation rate (point-biserial correlation coefficient [r pb ] = 0.85, p radiology. Using bibliometric knowledge, authors can craft a title, abstract, and text that may enhance visibility and citation count over what they would otherwise experience.

  9. Analysis of radiology education in undergraduate medical doctors training in Europe

    International Nuclear Information System (INIS)

    Kourdioukova, Elena V.; Valcke, Martin; Derese, Anselme; Verstraete, Koenraad L.

    2011-01-01

    Objectives: The purpose of the present study is to describe how undergraduate radiology teaching is organized in Europe and to identify important characteristics of undergraduate radiology curriculum. Methods: An electronic survey on undergraduate teaching was distributed by the European Society of Radiology (ESR) to 38 national delegates of the ESR Education Committee. Results: The 'classic type' of radiology teaching method is more frequent than the 'modular type'. In 38% of medical training centres the first experience with radiology is in pre-clinical years. The students enrolled in the fourth medical year experience the largest involvement in radiology education. The total number of teaching hours (mean 89 h, median 76 h) varies across the countries and differs depending on the radiological topic (mean across all topics 14.8 h, median 13). Written tests and oral exams were the most frequently used examination modes. Clerkships are reported as a key part of training. Conclusion: This first international comparative study of undergraduate radiological curriculum in Europe identifies a large number of differences in curriculum content and teaching methods throughout Europe. More research is needed to establish the radiological educational competences resulting from these differing curricula's to improve and to standardize the teaching according to (inter)national and institutional needs.

  10. Analysis of Operation Plumbbob nuclear test: BOLTZMANN radiological and meteorological data

    International Nuclear Information System (INIS)

    Steadman, C.R. Jr.; Kennedy, N.C.; Quinn, V.E.

    1983-09-01

    This report describes the Weather Service Nuclear Support Office (WSNSO) analyses of the radiological and meteorological data collected for the BOLTZMANN nuclear test of Operation PLUMBBOB. Inconsistencies in the radiological data and their resolution are discussed. The methods of converting aerial radiological data to equivalent ground-level values and of estimating fallout arrival times are presented. The meteorological situation on D-day is described. A comparison of the WSNSO fallout analyses with analyses in the late 1950's is presented. The appendices contain tabulated radiological data used in the fallout analyses, and contain discussions of the BOLTZMANN hot spot contention and of the enhanced activity at Portola, California

  11. Niagara pumping generation station inundation mapping and consequence analysis with ArcGIS and Mike 21

    Energy Technology Data Exchange (ETDEWEB)

    Grover, Patrick; Khayer, Yasmin; Naumov, Aleksey [4DM Inc., Toronto, (Canada); Zhang, Yibing [Ontario Power Generation, Toronto, (Canada)

    2010-07-01

    Inundation mapping is a key factor of Ontario Power Generation's dam safety program. It is the basis for determining the hazard potential classification of the dam by modelling the consequences of a hypothetical dam failure. This paper presented the project for updating the inundation mapping and consequence analysis study at the Niagara Pump generating station (PGS) reservoir. A complete hydrotechnical assessment of the Niagara PGS reservoir was conducted. The modelling of various breach scenarios was carried out using the 2-D hydrodynamic software MIKE 21 in order to provide the hydraulic data necessary for producing the inundation maps. Updated EPRP maps were produced and a consequence analysis was performed which confirmed the existing hazard classification. The ArcGIS system was used as the underlying framework for all major components of the project. It was found that the use of GIS technologies improve the efficiency of both modelling and analysis.

  12. Experimental Design and Data Analysis in Receiver Operating Characteristic Studies: Lessons Learned from Reports in Radiology from 1997 to 20061

    Science.gov (United States)

    Shiraishi, Junji; Pesce, Lorenzo L.; Metz, Charles E.; Doi, Kunio

    2009-01-01

    Purpose: To provide a broad perspective concerning the recent use of receiver operating characteristic (ROC) analysis in medical imaging by reviewing ROC studies published in Radiology between 1997 and 2006 for experimental design, imaging modality, medical condition, and ROC paradigm. Materials and Methods: Two hundred ninety-five studies were obtained by conducting a literature search with PubMed with two criteria: publication in Radiology between 1997 and 2006 and occurrence of the phrase “receiver operating characteristic.” Studies returned by the query that were not diagnostic imaging procedure performance evaluations were excluded. Characteristics of the remaining studies were tabulated. Results: Two hundred thirty-three (79.0%) of the 295 studies reported findings based on observers' diagnostic judgments or objective measurements. Forty-three (14.6%) did not include human observers, with most of these reporting an evaluation of a computer-aided diagnosis system or functional data obtained with computed tomography (CT) or magnetic resonance (MR) imaging. The remaining 19 (6.4%) studies were classified as reviews or meta-analyses and were excluded from our subsequent analysis. Among the various imaging modalities, MR imaging (46.0%) and CT (25.7%) were investigated most frequently. Approximately 60% (144 of 233) of ROC studies with human observers published in Radiology included three or fewer observers. Conclusion: ROC analysis is widely used in radiologic research, confirming its fundamental role in assessing diagnostic performance. However, the ROC studies reported in Radiology were not always adequate to support clear and clinically relevant conclusions. © RSNA, 2009 Supplemental material: http://radiology.rsna.org/lookup/suppl/doi:10.1148/radiol.2533081632/-/DC1 PMID:19864510

  13. Demonstration uncertainty/sensitivity analysis using the health and economic consequence model CRAC2

    International Nuclear Information System (INIS)

    Alpert, D.J.; Iman, R.L.; Johnson, J.D.; Helton, J.C.

    1985-01-01

    This paper summarizes a demonstration uncertainty/sensitivity analysis performed on the reactor accident consequence model CRAC2. The study was performed with uncertainty/sensitivity analysis techniques compiled as part of the MELCOR program. The principal objectives of the study were: 1) to demonstrate the use of the uncertainty/sensitivity analysis techniques on a health and economic consequence model, 2) to test the computer models which implement the techniques, 3) to identify possible difficulties in performing such an analysis, and 4) to explore alternative means of analyzing, displaying, and describing the results. Demonstration of the applicability of the techniques was the motivation for performing this study; thus, the results should not be taken as a definitive uncertainty analysis of health and economic consequences. Nevertheless, significant insights on health and economic consequence analysis can be drawn from the results of this type of study. Latin hypercube sampling (LHS), a modified Monte Carlo technique, was used in this study. LHS generates a multivariate input structure in which all the variables of interest are varied simultaneously and desired correlations between variables are preserved. LHS has been shown to produce estimates of output distribution functions that are comparable with results of larger random samples

  14. The Application of Strength of Association Statistics to the Item Analysis of an In-Training Examination in Diagnostic Radiology.

    Science.gov (United States)

    Diamond, James J.; McCormick, Janet

    1986-01-01

    Using item responses from an in-training examination in diagnostic radiology, the application of a strength of association statistic to the general problem of item analysis is illustrated. Criteria for item selection, general issues of reliability, and error of measurement are discussed. (Author/LMO)

  15. Radiological clerkships as a critical curriculum component in radiology education

    International Nuclear Information System (INIS)

    Kourdioukova, Elena V.; Verstraete, Koenraad L.; Valcke, Martin

    2011-01-01

    Objective: The aim of this research was to explore the perceived value of clinical clerkships in the radiology curriculum as well as the impact of radiology clerkship on students' beliefs about the profession of radiology as a whole and as a career. Methods: This study is a sequel to a previous survey in which student perceptions about radiology curriculum components were investigated. The present study focuses on a further analysis of a subsection in this study, based on 14 statements about radiology clerkship and two statements about radiology as a career. Results: Perceived usefulness of the aspects of radiology clerkship as 'radiology examination', 'skills development' and 'diagnosis focus' were awarded the highest scores. The predict value of the subscale 'radiology examination' on the level of performance was very high (adjusted R 2 = 0.19, p < .001). Conclusion: Students expressed highly favorable evaluation of clerkship as a learning environment to learn to order and to interpret imaging studies as well as an unique possibility to attend various radiological examinations and to access to specific radiology software systems, as well as to get a better view on radiology and to improve image interpretation skills. This positive attitude towards clerkship is closely tied to students' beliefs about the profession of radiology as a whole. These aspects of dedicated radiology clerkship are crucial for effective and high-quality education as well as for the choice of radiology as a career.

  16. Radiology applications of financial accounting.

    Science.gov (United States)

    Leibenhaut, Mark H

    2005-03-01

    A basic knowledge of financial accounting can help radiologists analyze business opportunities and examine the potential impacts of new technology or predict the adverse consequences of new competitors entering their service area. The income statement, balance sheet, and cash flow statement are the three basic financial statements that document the current financial position of the radiology practice and allow managers to monitor the ongoing financial operations of the enterprise. Pro forma, or hypothetical, financial statements can be generated to predict the financial impact of specific business decisions or investments on the profitability of the practice. Sensitivity analysis, or what-if scenarios, can be performed to determine the potential impact of changing key revenue, investment, operating cost or financial assumptions. By viewing radiology as both a profession and a business, radiologists can optimize their use of scarce economic resources and maximize the return on their financial investments.

  17. Analysis of radiological protection and security in the radioactive diagnosis area in a third level hospital

    International Nuclear Information System (INIS)

    Azorin Vega, J.C.; Aazorin Nieto, J.; Rivera Montalvo, T.

    1998-01-01

    Results from the evaluation made to radiological security and protection conditions prevailing in 13 medical diagnosis rooms with X rays at the National Nutrition Institute Zlavador Zubiran (third level hospital), aiming to give adequate protection and radiological security devices to the staff exposed from that hospital and to comply fully with requirements set by the standards

  18. A comparative analysis of radiological and surgical placement of central venous catheters

    International Nuclear Information System (INIS)

    McBride, Kieran D.; Fisher, Ross; Warnock, Neil; Winfield, David A.; Reed, Malcolm W.; Gaines, Peter A.

    1997-01-01

    Purpose. To compare the differences in practice and outcome of all radiologically and surgically placed central venous catheters retrospectively over a 2-year period simultaneously, at a single institution. Methods.A total of 253 Hickman catheters were inserted in 209 patients; 120 were placed radiologically in 102 patients and 133 were placed surgically in 107 patients. The indication was chemotherapy in 76% of radiological and in 47% of surgical cases; the remainder were for total parenteral nutrition and venous access. Results. There were 6 (4.5%) primary surgical failures and a further 17 (13%) surgical cases requiring multiple placement attempts. Pneumothorax occurred once (0.8%) surgically and four times (3.3%) radiologically. There were no radiological primary misplacements but there were five (3.7%) surgical ones. Catheter or central vein thrombosis occurred in four (3.3%) radiological and five (3.7%) surgical cases. The rate of infection per 1000 catheter-days was 1.9 in radiologically placed catheters and 4.0 in surgically placed ones (p<0.001). Average catheter life-span was similar for the two placement methods (100±23 days). Conclusion. Radiological placement is consistently more reliable than surgical placement. There are fewer placement complications and fewer catheter infections overall

  19. 324 Building Baseline Radiological Characterization

    Energy Technology Data Exchange (ETDEWEB)

    R.J. Reeder, J.C. Cooper

    2010-06-24

    This report documents the analysis of radiological data collected as part of the characterization study performed in 1998. The study was performed to create a baseline of the radiological conditions in the 324 Building.

  20. A survey of costs incurred in U.K. X-ray diffraction research laboratories as a consequence of proposed regulations for radiological safety

    International Nuclear Information System (INIS)

    Blow, D.M.

    1981-01-01

    A small survey of British X-ray diffraction laboratories was undertaken, with the aim of discovering the effects of the Health and Safety at Work Act (1974) and the draft regulations on radiological protection and ionising radiations (1978) on the practice of X-ray crystallography. The responses lead to the conclusion that the average cost incurred in bringing X-ray diffraction equipment to a safety standard compatible with the draft regulations (as judged by the respondents) will exceed Pound2,000 per X-ray generator. The safety costs will represent an overhead charge of at least 15-18% on the purchase of an X-ray generator, requiring additional capital outlay of over Pound5m to maintain the current level of X-ray diffraction activity in the U.K. There seems to be no evidence of a high accident rate with diffraction equipment, and the cost of the safety precautions bears no relation to the risks involved. (author)

  1. Estimation of the radiological consequences of dumping into the athmosphere and upon the surface waters caused by non-nuclear industrial processes in the Netherlands

    International Nuclear Information System (INIS)

    Punte, A.; Meijer, R.J. de; Put, L.W.

    1988-01-01

    The objective of this report is to make an estimation of the radiologic burden of the Dutch people caused by losses into the atmosphere and upon the surface waters by the non-nuclear industry in the Netherlands. All minerals and raw materials contain small quantities of radioactive materials. However, the concentrations in most minerals are small, the total amount of radioactivity can be considerable by using large amount of radioactivity can be considerable by using large amounts of minerals. As result from losses, storage and/or reuse of thhe rest materials liberated in these processes, a large part of the people may be exposed to an extra amount of ionizing radiation. In this report the risks and risk classes are formulated upon which the industrial brances may be subdivided. Therefore an estimation is made of the radionuclide-transport of the raw materials in various industrial branches. Next is is indicated how the amount of the losses from the radionuclide-transport can be estimated and how the limits of the risk classes can be translated into limits in the radionuclide-transport. Finally the risks for members of the critical groups and the general individual risks as result from the estimated losses and the from this resulting doses for distinguished industry branches. (author). 155 refs.; 6 figs.; 32 tabs

  2. Machine Learning and Radiology

    Science.gov (United States)

    Wang, Shijun; Summers, Ronald M.

    2012-01-01

    In this paper, we give a short introduction to machine learning and survey its applications in radiology. We focused on six categories of applications in radiology: medical image segmentation, registration, computer aided detection and diagnosis, brain function or activity analysis and neurological disease diagnosis from fMR images, content-based image retrieval systems for CT or MRI images, and text analysis of radiology reports using natural language processing (NLP) and natural language understanding (NLU). This survey shows that machine learning plays a key role in many radiology applications. Machine learning identifies complex patterns automatically and helps radiologists make intelligent decisions on radiology data such as conventional radiographs, CT, MRI, and PET images and radiology reports. In many applications, the performance of machine learning-based automatic detection and diagnosis systems has shown to be comparable to that of a well-trained and experienced radiologist. Technology development in machine learning and radiology will benefit from each other in the long run. Key contributions and common characteristics of machine learning techniques in radiology are discussed. We also discuss the problem of translating machine learning applications to the radiology clinical setting, including advantages and potential barriers. PMID:22465077

  3. Machine learning and radiology.

    Science.gov (United States)

    Wang, Shijun; Summers, Ronald M

    2012-07-01

    In this paper, we give a short introduction to machine learning and survey its applications in radiology. We focused on six categories of applications in radiology: medical image segmentation, registration, computer aided detection and diagnosis, brain function or activity analysis and neurological disease diagnosis from fMR images, content-based image retrieval systems for CT or MRI images, and text analysis of radiology reports using natural language processing (NLP) and natural language understanding (NLU). This survey shows that machine learning plays a key role in many radiology applications. Machine learning identifies complex patterns automatically and helps radiologists make intelligent decisions on radiology data such as conventional radiographs, CT, MRI, and PET images and radiology reports. In many applications, the performance of machine learning-based automatic detection and diagnosis systems has shown to be comparable to that of a well-trained and experienced radiologist. Technology development in machine learning and radiology will benefit from each other in the long run. Key contributions and common characteristics of machine learning techniques in radiology are discussed. We also discuss the problem of translating machine learning applications to the radiology clinical setting, including advantages and potential barriers. Copyright © 2012. Published by Elsevier B.V.

  4. Probabilistic accident consequence uncertainty analysis: Food chain uncertainty assessment. Volume 2: Appendices

    Energy Technology Data Exchange (ETDEWEB)

    Brown, J. [National Radiological Protection Board (United Kingdom); Goossens, L.H.J.; Kraan, B.C.P. [Delft Univ. of Technology (Netherlands)] [and others

    1997-06-01

    This volume is the second of a two-volume document that summarizes a joint project by the US Nuclear Regulatory and the Commission of European Communities to assess uncertainties in the MACCS and COSYMA probabilistic accident consequence codes. These codes were developed primarily for estimating the risks presented by nuclear reactors based on postulated frequencies and magnitudes of potential accidents. This two-volume report, which examines mechanisms and uncertainties of transfer through the food chain, is the first in a series of five such reports. A panel of sixteen experts was formed to compile credible and traceable uncertainty distributions for food chain transfer that affect calculations of offsite radiological consequences. Seven of the experts reported on transfer into the food chain through soil and plants, nine reported on transfer via food products from animals, and two reported on both. The expert judgment elicitation procedure and its outcomes are described in these volumes. This volume contains seven appendices. Appendix A presents a brief discussion of the MAACS and COSYMA model codes. Appendix B is the structure document and elicitation questionnaire for the expert panel on soils and plants. Appendix C presents the rationales and responses of each of the members of the soils and plants expert panel. Appendix D is the structure document and elicitation questionnaire for the expert panel on animal transfer. The rationales and responses of each of the experts on animal transfer are given in Appendix E. Brief biographies of the food chain expert panel members are provided in Appendix F. Aggregated results of expert responses are presented in graph format in Appendix G.

  5. Probabilistic accident consequence uncertainty analysis: Food chain uncertainty assessment. Volume 2: Appendices

    International Nuclear Information System (INIS)

    Brown, J.; Goossens, L.H.J.; Kraan, B.C.P.

    1997-06-01

    This volume is the second of a two-volume document that summarizes a joint project by the US Nuclear Regulatory and the Commission of European Communities to assess uncertainties in the MACCS and COSYMA probabilistic accident consequence codes. These codes were developed primarily for estimating the risks presented by nuclear reactors based on postulated frequencies and magnitudes of potential accidents. This two-volume report, which examines mechanisms and uncertainties of transfer through the food chain, is the first in a series of five such reports. A panel of sixteen experts was formed to compile credible and traceable uncertainty distributions for food chain transfer that affect calculations of offsite radiological consequences. Seven of the experts reported on transfer into the food chain through soil and plants, nine reported on transfer via food products from animals, and two reported on both. The expert judgment elicitation procedure and its outcomes are described in these volumes. This volume contains seven appendices. Appendix A presents a brief discussion of the MAACS and COSYMA model codes. Appendix B is the structure document and elicitation questionnaire for the expert panel on soils and plants. Appendix C presents the rationales and responses of each of the members of the soils and plants expert panel. Appendix D is the structure document and elicitation questionnaire for the expert panel on animal transfer. The rationales and responses of each of the experts on animal transfer are given in Appendix E. Brief biographies of the food chain expert panel members are provided in Appendix F. Aggregated results of expert responses are presented in graph format in Appendix G

  6. The radiological consequences of notional accidental releases of radioactivity from fast breeder reactors: sensitivity to the dose-effect relationships adopted for early biological effects

    International Nuclear Information System (INIS)

    Kelly, G.N.; Simmonds, J.R.; Smith, H.; Stather, J.W.

    1979-07-01

    This study considered the sensitivity to the dose-response relationships adopted for the estimation of early biological effects from notional accidental releases of radioactivity from fast breeder reactors. Two distinct aspects were considered: the sensitivity of the predicted consequences to variation in the dose-mortality relationships for irradiation of the bone marrow and the lung; and the influence of simple supportive medical treatment in reducing the incidence of early deaths in the exposed population. The numbers of early effects estimated in the initial study were relatively insensitive to variation in the dose-mortality relationships within the bounds proposed. The few exceptions concerned releases of particular nuclide composition, and the variation in the predicted consequences could be around an order of magnitude; the absolute numbers of effects however were in general small when the sensitivity was most pronounced. The reduction in the incidence of early deaths when using simple supportive treatment varied markedly with the nuclide composition of the release. Areas of uncertainty were identified where further research and investigation might most profitably be directed with a view to improving the reliability of the dose-effect relationships adopted and hence of the predicted consequences of the release considered. (author)

  7. Consequence analysis of IWTS metal water reactions (Fauske and Associates report 99-35)

    International Nuclear Information System (INIS)

    DUNCAN, D.R.

    1999-01-01

    The report describes the consequences of postulated thermally unstable conditions in the IWTS knock out pot. The consequence analysis shows that both the knock out pot and particulate bed will stay intact, and that releases will be minor. Reaction rate limitations prevent knock out pot pressure and/or temperature from even approaching values that would threaten structural integrity. Source term calculations based on a particle bed with a homogeneous mixture of metal and oxide particles yield a release above the K Basin pool of about 12 grams

  8. Rational use of diagnostic radiology

    International Nuclear Information System (INIS)

    Racoveanu, N.T.; Volodin, V.

    1992-01-01

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

  9. Uncertainty Analysis on the Health Risk Caused by a Radiological Terror

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  10. Analysis of data relative to the update of diagnostic reference levels in radiology and nuclear medicine. 2011-2012 review

    International Nuclear Information System (INIS)

    2014-01-01

    Applying the Order of 24 October 2011 on diagnostic reference levels, departments of radiology and nuclear medicine must send a sample of 'patient' dosimetric data to the IRSN each year. The results of the analysis of dosimetric data performed between the 1 January 2011 and the 31 December 2012 presented in this report should enable the authority to define the needs for updating regulations. Professional involvement in DRLs improved globally over the 2011-2012 period but is heterogeneous according to the imaging area considered. The participation of conventional radiology professionals is still low, with less than 30% against over 75% in CT and 85% in nuclear medicine. Data collection in pediatrics, considering all the fields of medical imaging, remains extremely limited. This shows almost no dose assessment for children by imaging departments, and has the effect of not allowing authorities to provide professionals with DRLs representative of pediatric practices. The analysis of radiology doses and nuclear medicine administered activities by IRSN shows an overall decrease of statistical indicators on which DRLs are indexed. These results lead to proposals for updating reference values for a large number of examinations. In addition to the analysis of data collected for examinations currently mentioned in regulatory texts, IRSN recommends to update DRLs in a more general way by changing the strategy for collecting and updating pediatric DRLs, by including interventional radiology - specialty in which the radiation protection presents a major challenge - by introducing a more ambitious indicator than the 75. percentile in conventional radiology and nuclear medicine - the 25. percentile statistical indicator, and by taking into account new technologies inducing additional exposures to the patient as CT-scan associated with the PET. (authors)

  11. The effects of actinide separation on the radiological consequences of disposal of high-level radioactive waste on the ocean bed

    International Nuclear Information System (INIS)

    Camplin, W.C.; Grimwood, P.D.; White, I.F.

    1980-01-01

    One option in the management of high-level radioactive wastes is to separate the actinides prior to vitrification and disposal. This option is examined in the context of disposal of high-level wastes on the deep ocean bed. The initial quantity of waste corresponds to the generation of 1000 GW(e)y of nuclear energy, and the actinide-separation process is assumed to remove 99% of all elements of atomic number greater than that of actinium. The models used to describe the dispersion of activity from a single disposal site on the bed of the Atlantic Ocean represent both local dispersion and long-term mixing. Collective doses and doses to individuals are calculated for six potential pathways: ingestion of fish, crustacea, molluscs, plankton and seaweed, and external irradiation from contaminated beach sediments. The period from 400 to 1,000,000 years after disposal is considered. The potential radiological impact from disposal of high-level waste without separation of actinides on the ocean bed arises from the actinides; isotopes of americium, neptunium and plutonium give the highest doses. Actinide separation would reduce these doses in proportion to the effectiveness of the separation process, until doses become determined by fission products rather than actinides: the achievable dose reduction would be a factor of approximately a hundred, or less for certain pathways. This reduction applies only to doses to the public from waste disposal: no account was taken of doses arising from the separation process itself or from the management of the separated actinides. The results of the assessment are contrasted with those of similar studies based on toxicity indices. Major deficiencies are identified in the use of toxicity indices as a basis for decision-making. (author)

  12. Agreement between the Swiss Federal Council and the Government of the French Republic on exchange of information in case of an accident that might have radiological consequences

    International Nuclear Information System (INIS)

    1979-10-01

    This Agreement which came into force by an exchange of notes on 13 December 1979 provides in particular, for the setting up of a mechanism for communications on emergency situations in the territories of both countries which are likely to have radiation consequences. Mutual alarm centres will be set up both in France and in Switzerland, and representatives of each country may be appointed to the competent services of the other country. Information on emergency situations must be supplemented by additional data on existing or planned measures to protect the population in the country concerned. (NEA) [fr

  13. Interventional Radiology of Male Varicocele: Current Status

    International Nuclear Information System (INIS)

    Iaccarino, Vittorio; Venetucci, Pietro

    2012-01-01

    Varicocele is a fairly common condition in male individuals. Although a minor disease, it may cause infertility and testicular pain. Consequently, it has high health and social impact. Here we review the current status of interventional radiology of male varicocele. We describe the radiological anatomy of gonadal veins and the clinical aspects of male varicocele, particularly the physical examination, which includes a new clinical and ultrasound Doppler maneuver. The surgical and radiological treatment options are also described with the focus on retrograde and antegrade sclerotherapy, together with our long experience with these procedures. Last, we compare the outcomes, recurrence and persistence rates, complications, procedure time and cost-effectiveness of each method. It clearly emerges from this analysis that there is a need for randomized multicentre trials designed to compare the various surgical and percutaneous techniques, all of which are aimed at occlusion of the anterior pampiniform plexus.

  14. Interventional Radiology of Male Varicocele: Current Status

    Energy Technology Data Exchange (ETDEWEB)

    Iaccarino, Vittorio, E-mail: vittorio.iaccarino@unina.it; Venetucci, Pietro [University of Naples ' Federico II' , Diagnostic Imaging Department-Cardiovascular and Interventional Radiology, School of Medicine (Italy)

    2012-12-15

    Varicocele is a fairly common condition in male individuals. Although a minor disease, it may cause infertility and testicular pain. Consequently, it has high health and social impact. Here we review the current status of interventional radiology of male varicocele. We describe the radiological anatomy of gonadal veins and the clinical aspects of male varicocele, particularly the physical examination, which includes a new clinical and ultrasound Doppler maneuver. The surgical and radiological treatment options are also described with the focus on retrograde and antegrade sclerotherapy, together with our long experience with these procedures. Last, we compare the outcomes, recurrence and persistence rates, complications, procedure time and cost-effectiveness of each method. It clearly emerges from this analysis that there is a need for randomized multicentre trials designed to compare the various surgical and percutaneous techniques, all of which are aimed at occlusion of the anterior pampiniform plexus.

  15. Radiological English

    Energy Technology Data Exchange (ETDEWEB)

    Ribes, R. [Hospital Reina Sofia, Cordoba (Spain). Servicio de Radiologia; Ros, P.R. [Harvard Medical School, Boston, MA (United States). Div. of Radiology

    2007-07-01

    The book is an introductory book to radiological English on the basis that there are a lot of radiologists, radiology residents, radiology nurses, radiology students, and radiographers worldwide whose English level is indeterminate because their reading skills are much higher than their fluency. It is intended to help those health care professionals who need English for their work but do not speak English on a day-to-day basis. (orig.)

  16. Radiological English

    International Nuclear Information System (INIS)

    Ribes, R.; Ros, P.R.

    2007-01-01

    The book is an introductory book to radiological English on the basis that there are a lot of radiologists, radiology residents, radiology nurses, radiology students, and radiographers worldwide whose English level is indeterminate because their reading skills are much higher than their fluency. It is intended to help those health care professionals who need English for their work but do not speak English on a day-to-day basis. (orig.)

  17. Radiological analysis by the addition of hydrogen and noble metals in the reactors of the Laguna Verde central

    International Nuclear Information System (INIS)

    Padilla C, I.

    2006-01-01

    During the operation of the nuclear power stations there are metals that are subject to condition and agents that cause that these they present indications of intergranular corrosion and for their importance they are subject to a continuous surveillance to assure their integrity. During the time of operation, for the level of indications, it can be necessary the substitution of these. The internal components of the vessel and particularly those of the structure of the reactor core are exposed during the operation to a neutron flow that causes that these they are activated and, in consequence, before an eventual repair it will be necessary to face high radiation levels. At the moment a technique that controls exists and it reduces the growth rate of the indications in the metals and it increases its useful life: the addition of hydrogen. The addition of hydrogen it is an ALARA measure from long term when protecting the internals of the vessel that requires to establish radiological controls in the stage of their application to avoid unnecessary dose to the personnel. The addition of hydrogen to the primary system has as objective to reduce the growth of indications taken place by intergranular corrosion in metals of the reactor core and this is achieved when the electrochemical thresholds are reached. Hydrogen to interacting with the metal surfaces it generates reductive reactions causing in consequence an increment in the concentration of soluble cobalt in the coolant one and an increment in the nitrogen concentration. To reduce the magnitude of the radiological impact that in some NC reach up to factors 10, its are injected to the system noble metals as the rhodium and the platinum, to reduce the concentration of hydrogen to the system and to be below the threshold electrochemical potential necessary to protect the internals of the reactor vessel. The external and internal operational experience generated on this protection technique to the internals of the vessel

  18. Comparative analysis of chest radiological findings between avian human influenza and SARS

    International Nuclear Information System (INIS)

    Cai Mingjin; Mai Weiwen; Xian Jianxing; Zhang Jiayun; Lin Wenjian; Wei Liping; Chen Jincheng

    2008-01-01

    Objective: To study the chest radiological findings of a mortal avian human influenza case. Methods: One patient in our hospital was proved to be infected avian human influenza in Guangdong province on March 1, 2006. The Clinical appearances and chest radiological findings of this case were retrospectively analyzed and compared with that of 3 mortal SARS cases out of 16 cases in 2003. Results: Large consolidated areas in left lower lobe was showed in pulmonary radiological findings of this patient and soon developed into ARDS (adult respiratory distress syndrome). However, the pulmonary radiological findings had no characteristic. Characteristics of soaring size and number during short term appeared in SARS instead of avian human influenza. Final diagnosis was up to the etiology and serology examination. Conclusion: Bronchial dissemination was not observed in this avian human influenza case. Pay attention to the avian human influenza in spite of no history of contract with sick or dead poultry in large city. (authors)

  19. A survey of ponticulus posticus: Radiological analysis of atlas in an ...

    African Journals Online (AJOL)

    2015-08-06

    Aug 6, 2015 ... Department of Orthodontics, Faculty of Dentistry, Ordu University,. 52100 Ordu ... atlas is a ring‑like structure consisting of two lateral masses connected by a ... Radiology Department at the Erciyes University, Kayseri,. Turkey.

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

    International Nuclear Information System (INIS)

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

    2013-01-01

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

  1. Analysis of data relative to the update of diagnostic reference levels in radiology and nuclear medicine. 2013-2015 review

    International Nuclear Information System (INIS)

    2016-11-01

    Applying the Order of 24 October 2011 on diagnostic reference levels, departments of radiology and nuclear medicine must send a sample of 'patient' dosimetric data to the IRSN each year. The results of the analysis of dosimetric data performed between the 1 January 2013 and the 31 December 2015 presented in this report should enable the authority to define the needs for updating regulation. This assessment takes place in a national and international context particularly rich and active since the last years. More than 20 years after the official introduction of the DRL concept by ICRP and the first regulation requirements at a European level, the good and the bad sides of the DRLs systems implemented by several countries, including France, has shown the necessity of complementary actions regarding some specific practices (pediatrics, interventional radiology). On one hand, from a national point of view, the current collection and analysis system is highly efficient for evaluation of practices in France and for DRL update ability. On the other hand, as an optimization implementation tool, regarding the lack of professionals involvement, the current system should not be considered as fully effective in radiology. However, when the professionals carry out DRL data collection and analysis, optimization actions are implemented for nearly all the cases. During the 2013-2015 period, professionals involvement in DRLs globally improved but is heterogeneous according to the imaging area considered. The participation of conventional radiology professionals is still low, with less than 30% against about 80% in CT and more than 85% in nuclear medicine. From a dosimetric point of view, the national analysis shows an overall decrease of statistical indicators in radiology, computed tomography and nuclear medicine on which DRLs are indexed. These results lead to proposals for updating reference values for a large number of examinations. In addition to the analysis of data collected

  2. Fast neutron background characterization with the Radiological Multi-sensor Analysis Platform (RadMAP)

    Energy Technology Data Exchange (ETDEWEB)

    Davis, John R., E-mail: john.davis@usma.edu [Lawrence Berkeley National Laboratory, Berkeley, CA (United States); The United States Military Academy, West Point, NY (United States); Brubaker, Erik [Sandia National Laboratories, Livermore, CA (United States); Vetter, Kai [Lawrence Berkeley National Laboratory, Berkeley, CA (United States)

    2017-06-21

    In an effort to characterize the fast neutron radiation background, 16 EJ-309 liquid scintillator cells were installed in the Radiological Multi-sensor Analysis Platform (RadMAP) to collect data in the San Francisco Bay Area. Each fast neutron event was associated with specific weather metrics (pressure, temperature, absolute humidity) and GPS coordinates. The expected exponential dependence of the fast neutron count rate on atmospheric pressure was demonstrated and event rates were subsequently adjusted given the measured pressure at the time of detection. Pressure adjusted data was also used to investigate the influence of other environmental conditions on the neutron background rate. Using National Oceanic and Atmospheric Administration (NOAA) coastal area lidar data, an algorithm was implemented to approximate sky-view factors (the total fraction of visible sky) for points along RadMAPs route. Three areas analyzed in San Francisco, Downtown Oakland, and Berkeley all demonstrated a suppression in the background rate of over 50% for the range of sky-view factors measured. This effect, which is due to the shielding of cosmic-ray produced neutrons by surrounding buildings, was comparable to the pressure influence which yielded a 32% suppression in the count rate over the range of pressures measured.

  3. Radiological and genetic analysis of a Late Iron Age mummy from the Tuli Block, Botswana

    Directory of Open Access Journals (Sweden)

    Frank J. Rühli

    2016-02-01

    Full Text Available Mummified human remains are valuable sources of information on past populations. Here we report on the radiological and molecular findings of a partially mummified individual found in northern Botswana. This desiccated mummy from the Tuli region is the first to have been reported from this region. The remains were those of an older male adult of African origin. He was interred in a tightly flexed position and wrapped in an animal skin. Computerised tomography (CT scanning revealed that none of the internal organs was preserved. Multiple post-mortem alterations are seen, but apart from some degenerative changes of the lower vertebral column, the axial skeleton has remained intact. The advanced osteophytosis suggests an older age than what was previously estimated. The aDNA analysis confirms Sotho-Tswana and possibly Khoesan genetic relatedness, as could be expected from individuals from that region. These results represent one of the first CT scans of a mummified individual from southern Africa, and also the first successful aDNA extraction from such remains.

  4. A Current Review of the Meniscus Imaging: Proposition of a Useful Tool for Its Radiologic Analysis

    Directory of Open Access Journals (Sweden)

    Nicolas Lefevre

    2016-01-01

    Full Text Available The main objective of this review was to present a synthesis of the current literature in order to provide a useful tool to clinician in radiologic analysis of the meniscus. All anatomical descriptions were clearly illustrated by MRI, arthroscopy, and/or drawings. The value of standard radiography is extremely limited for the assessment of meniscal injuries but may be indicated to obtain a differential diagnosis such as osteoarthritis. Ultrasound is rarely used as a diagnostic tool for meniscal pathologies and its accuracy is operator-dependent. CT arthrography with multiplanar reconstructions can detect meniscus tears that are not visible on MRI. This technique is also useful in case of MRI contraindications, in postoperative assessment of meniscal sutures and the condition of cartilage covering the articular surfaces. MRI is the most accurate and less invasive method for diagnosing meniscal lesions. MRI allows confirming and characterizing the meniscal lesion, the type, the extension, its association with a cyst, the meniscal extrusion, and assessing cartilage and subchondral bone. New 3D-MRI in three dimensions with isotropic resolution allows the creation of multiplanar reformatted images to obtain from an acquisition in one sectional plane reconstructions in other spatial planes. 3D MRI should further improve the diagnosis of meniscal tears.

  5. A Current Review of the Meniscus Imaging: Proposition of a Useful Tool for Its Radiologic Analysis

    Science.gov (United States)

    Lefevre, Nicolas; Naouri, Jean Francois; Herman, Serge; Gerometta, Antoine; Klouche, Shahnaz; Bohu, Yoann

    2016-01-01

    The main objective of this review was to present a synthesis of the current literature in order to provide a useful tool to clinician in radiologic analysis of the meniscus. All anatomical descriptions were clearly illustrated by MRI, arthroscopy, and/or drawings. The value of standard radiography is extremely limited for the assessment of meniscal injuries but may be indicated to obtain a differential diagnosis such as osteoarthritis. Ultrasound is rarely used as a diagnostic tool for meniscal pathologies and its accuracy is operator-dependent. CT arthrography with multiplanar reconstructions can detect meniscus tears that are not visible on MRI. This technique is also useful in case of MRI contraindications, in postoperative assessment of meniscal sutures and the condition of cartilage covering the articular surfaces. MRI is the most accurate and less invasive method for diagnosing meniscal lesions. MRI allows confirming and characterizing the meniscal lesion, the type, the extension, its association with a cyst, the meniscal extrusion, and assessing cartilage and subchondral bone. New 3D-MRI in three dimensions with isotropic resolution allows the creation of multiplanar reformatted images to obtain from an acquisition in one sectional plane reconstructions in other spatial planes. 3D MRI should further improve the diagnosis of meniscal tears. PMID:27057352

  6. Radiology fundamentals

    CERN Document Server

    Singh, Harjit

    2011-01-01

    ""Radiology Fundamentals"" is a concise introduction to the dynamic field of radiology for medical students, non-radiology house staff, physician assistants, nurse practitioners, radiology assistants, and other allied health professionals. The goal of the book is to provide readers with general examples and brief discussions of basic radiographic principles and to serve as a curriculum guide, supplementing a radiology education and providing a solid foundation for further learning. Introductory chapters provide readers with the fundamental scientific concepts underlying the medical use of imag

  7. Bibliometric Analysis of Manuscript Title Characteristics Associated With Higher Citation Numbers: A Comparison of Three Major Radiology Journals, AJNR, AJR, and Radiology.

    Science.gov (United States)

    Chokshi, Falgun H; Kang, Jian; Kundu, Suprateek; Castillo, Mauricio

    Our purpose was to determine if associations exist between titles characteristics and citation numbers in Radiology, American Journal of Roentgenology (AJR), and American Journal of Neuroradiology (AJNR). This retrospective study is Institutional Review Board exempt. We searched Web of Science for all original research and review articles in Radiology, AJR, and AJNR between 2006 and 2012 and tabulated number of words in the title, presence of a colon symbol, and presence of an acronym. We used a Poisson regression model to evaluate the association between number of citations and title characteristics. We then used the Wald test to detect pairwise differences in the effect of title characteristics on number of citations among the 3 journals. Between 2006 and 2012, Radiology published 2662, AJR 3998, and AJNR 2581 original research and review articles. There was a citation number increase per title word increase of 1.6% for AJNR and 2.6% for AJR and decrease of 0.8% for Radiology. For all, P citation increases for AJNR (16%), Radiology (14%), and AJR (7.4%). Title acronym was associated with citation increases for AJNR (10%), Radiology (14%), and AJR (13.3%). All P citation numbers in Radiology, AJR, and AJNR. Copyright © 2016 Elsevier Inc. All rights reserved.

  8. Radiation protection during decommissioning of the salt cavern Asse II. Recommendations by the German Commission on radiological protection; Strahlenschutz bei der Stilllegung der Schachtanlage Asse II. Empfehlung der Strahlenschutzkommission

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2016-09-15

    The recommendations by the German Commission on radiological protection concerning radiation protection during decommissioning of the salt cavern Asse II include the following issues: radiological consequences of non-controllable solution ingress, optional decommissioning modes, basis requirements of decommissioning, fact evaluation, determination of radiation exposure, radiological requirements for long-term safety, analysis of consequences and long-term safety demonstration, data and information, emergency protection, public transparency.

  9. Collaborative Radiological Response Planning

    Science.gov (United States)

    2013-12-01

    DOE and EPA national laboratories .55 Additionally, the GAO conducted a survey of emergency management officials in cities, states and federal...for Biosecurity of UPMC, (2012). After fukushima: Managing the consequences of a radiological release. Retrieved from : http://issuu.com

  10. Meta-analysis of the antecedent and consequent constructs of materialism

    OpenAIRE

    Fernando de Oliveira Santini; Wagner Júnior Ladeira; Cláudio Hoffmann Sampaio; Clécio Falcão Araújo

    2017-01-01

    Purpose – Materialism has been gaining ground in the academic field, especially from the 1980s on, given the relevance of understanding sentiments connected to possessing and acquiring goods. Thus, this meta-analysis was carried out to assess the antecedents and consequents of materialism. Design/methodology/approach – Based on a systematic review, we gathered a total 77 articles that examined those aspects, generating 99 effects-sizes and a cumulative sample of 40,288 studied individuals...

  11. Aspects of risk analysis application to estimation of nuclear accidents and tests consequences and intervention management

    International Nuclear Information System (INIS)

    Demin, V.F.; Hedemann-Jensen, P.; Rolevich, I.V.; Schneider, T.S.; Sobolev, B.G.

    1996-01-01

    For assessment of accident consequences and a post-accident management a risk analysis methodology and data bank (BARD) with allowance for radiation and non-radiation risk causes should be developed and used. Aspects of these needs and developments are considered. Some illustrative results of health risk estimation made with BARD for the Bryansk region territory with relatively high radioactive contamination from the Chernobyl accident are presented

  12. The top 100 articles in the radiology of trauma: a bibliometric analysis.

    Science.gov (United States)

    Dolan, Ryan Scott; Hanna, Tarek N; Warraich, Gohar Javed; Johnson, Jamlik-Omari; Khosa, Faisal

    2015-12-01

    The purpose of this study was to identify the 100 top-cited articles in the radiology of trauma, analyze the resulting database to understand factors resulting in highly cited works, and establish trends in trauma imaging. An initial database was created via a Web of Science (WOS) search of all scientific journals using the search terms "trauma" and either "radiology" or a diagnostic modality. Articles were ranked by citation count and screened by two attending radiologists plus a tiebreaker for appropriateness. The following information was collected from each article: WOS all database citations, year, journal, authors, department affiliation, study type and design, sample size, imaging modality, subspecialty, organ, and topic. Citations for the top 100 articles ranged from 82-252, and citations per year ranged from 2.6-37.2. A plurality of articles were published in the 1990s (n = 45) and 1980s (n = 31). Articles were published across 24 journals, most commonly Radiology (n = 31) and Journal of Trauma-Injury, Infection, and Critical Care (n = 28). Articles had an average of five authors and 35 % of first authors were affiliated with a department other than radiology. Forty-six articles had sample sizes of 100 or fewer. Computed tomography (CT) was the most common modality (n = 67), followed by magnetic resonance (MR; n = 22), and X-ray (XR; n = 11). Neuroradiology (n = 48) and abdominal radiology (n = 36) were the most common subspecialties. The 100 top-cited articles in the radiology of trauma are diverse. Subspecialty bibliometric analyses identify the most influential articles of a particular field, providing more implications to clinical radiologists, trainees, researchers, editors, and reviewers than radiology-wide lists.

  13. Release consequence analysis for a hypothetical geologic radioactive waste repository in salt

    International Nuclear Information System (INIS)

    1979-08-01

    One subtask conducted under the INFCE program is to evaluate and compare the health and safety impacts of different fuel cycles in which all radioactive wastes (except those from mining and milling) are placed in a geologic repository in salt. To achieve this objective, INFCE Working Group 7 examined the radiologic dose to humans from geologic repositories containing waste arisings as defined for seven reference fuel cycles. This report examines the release consequences for a generic waste repository in bedded salt. The top of the salt formation and the top of the repository are assumed to be 250 and 600 m, respectively, below the surface. The hydrogeologic structure above the salt consists of two aquifers and two aquitards. The aquifers connect to a river 6.2 km from the repository. The regional gradient to the river is 1 m/km in all aquifers. Hydrologic, transport, and dose models were used to model two release scenarios for each fuel cycle, one without a major disturbance and one in which a major geologic perturbation breached the repository immediately after it was sealed. The purpose of the modeling was to predict the rate of transport of radioactive contaminants from the repository through the geosphere to the biosphere, and to determine the potential dose to humans. Of the many radionuclides in the waste, only 129 I and 226 Ra arrived at the river in sufficient concentrations for a measurable dose calculation. Radionuclide concentrations in the ground water pose no threat to man because the ground water is a concentrated brine and it is diluted by a factor of 10 6 to 10 7 upon entering the river

  14. Consequence Analysis of Release from KN-18 Cask during a Severe Transportation Accident

    International Nuclear Information System (INIS)

    Lim, Heoksoon; Bhang, Giin; Na, Janghwan; Ban, Jaeha; Kim, Myungsu

    2015-01-01

    Korea Hydro and Nuclear Power (KHNP) has launched a project entitled 'Development of APR1400 Physical Protection System Design' and conducting a new conceptual physical protection system(PPS) design. One of mayor contents is consequence analysis for spent nuclear fuel cask. Proper design of physical protection system for facilities and storage and transformation involving nuclear and radioactive material requires the quantification of potential consequence from prescribed sabotage and theft scenarios in order to properly understand the level of PPS needed for specific facilities and materials. An important aspect of the regulation of the nuclear industry is assessing the risk to the public and the environment from a release of radioactive material produced by accidental or intentional scenarios. This paper describes the consequence analysis methodology, structural analysis for KN-18 cask and results of release from the cask during a severe transportation accident. Accident during spent fuel cask transportation was numerically calculated for KN-18, and showed the integrity of the fuel assemblies and cask itself was unharmed on a scenario that is comparable to state of art NRC research. Even assumption of leakage as a size of 1 x 10''2 mm''2 does not exceed for a certain criteria at any distance

  15. Consequence Analysis of Release from KN-18 Cask during a Severe Transportation Accident

    Energy Technology Data Exchange (ETDEWEB)

    Lim, Heoksoon; Bhang, Giin; Na, Janghwan; Ban, Jaeha; Kim, Myungsu [KAERI, Daejeon (Korea, Republic of)

    2015-05-15

    Korea Hydro and Nuclear Power (KHNP) has launched a project entitled 'Development of APR1400 Physical Protection System Design' and conducting a new conceptual physical protection system(PPS) design. One of mayor contents is consequence analysis for spent nuclear fuel cask. Proper design of physical protection system for facilities and storage and transformation involving nuclear and radioactive material requires the quantification of potential consequence from prescribed sabotage and theft scenarios in order to properly understand the level of PPS needed for specific facilities and materials. An important aspect of the regulation of the nuclear industry is assessing the risk to the public and the environment from a release of radioactive material produced by accidental or intentional scenarios. This paper describes the consequence analysis methodology, structural analysis for KN-18 cask and results of release from the cask during a severe transportation accident. Accident during spent fuel cask transportation was numerically calculated for KN-18, and showed the integrity of the fuel assemblies and cask itself was unharmed on a scenario that is comparable to state of art NRC research. Even assumption of leakage as a size of 1 x 10''2 mm''2 does not exceed for a certain criteria at any distance.

  16. Preliminary analysis of doses to evaluate the image quality in radiographic examinations in veterinary radiology

    International Nuclear Information System (INIS)

    Pinto, Ana Carolina B.C.F.; Dias, Mayara T.P.; Santos, Andrea C.; Melo, Camila S.; Furquim, Tania A.C.

    2009-01-01

    This work has as objective to promote the analysis of the radiological doses and quality of the image of the technical letter used for the accomplishment of thorax and coxal radiographic examination of animals of canine and feline species. The study was accomplished in the service of Diagnosis for Image in Veterinarian Hospital of Veterinary Medicine and Zootecnia College of University of Sao Paulo, in two conventional equipment. Initially, physical features of the animals and the technique used were collected for each one of the 188 radiographic examinations of thorax and 52 examinations of coxal. The animals were placed in different groups, according to their body weight. For each group, the averages for each feature were calculated: thickness of the radiographed region, tension, electric current, time of exhibition, current product electric-time, size of the used film, presence or absence of bucky and feature of focus (narrow or thick). On the basis of the averages of group M (of lesser weights that 5kg for cats and between 10,1kg and 20kg for dogs), was executed a physical analysis of the current technical letter, using the equipment: ionization chamber (to determinate the value of kerma in air), simulator objects (representative of the thickness of the animal) and three dispositive standards of test that evaluate space resolution, resolution in low contrast and contrast-detail. The obtained images were analyzed and compared for a physicist and a radiologist medical veterinary. The results had shown that the examinations supply dose considered high for techniques used mainly for coxal. The equipment A, although to supply higher doses, presents the better images for the majority of the projections. However, the study indicates that there are not exactly reference levels, but these examinations must pass for improvement of quality of image (author)

  17. Radiological impacts analysis with use of new endpoint as complementary safety indicators

    International Nuclear Information System (INIS)

    Peralta Vital, J.L.; Gil Castillo, R.; Fleitas Estevez, G.G.; Olivera Acosta, J.

    2015-01-01

    The paper shows the new safety indicators on risk assessment (safety assessment) to radioactive waste environmental management implementation (concentrations and fluxes of naturally occurring radioactive materials (NORM)). The endpoint obtained, allow the best analysis of the radiological impact associated to radioactive waste isolation system. The common safety indicators for safety assessment purpose, dose and risk, are very time dependent, increasing the uncertainties in the results for long term assessment. The complementary and new proposed endpoints are more stable and they are not affected by changes in the critical group, pathways, etc. The NORM values on facility site were obtained as result of national surveys, the natural concentrations of U, Ra, Th, K has been associated with the variation of the lithologies in 3 geographical areas of the Country (Occidental, Central and Oriental). The results obtained are related with the safety assessment topics and allowed to apply the new complementary safety indicators, by comparisons between the natural concentrations and fluxes on site and its calculated values for the conceptual repository design. In order to normalize the concentration results, the analysis was realized adopting the criteria of the Repository Equivalent Rock Volume (RERV). The preliminary comparison showed that the calculated concentrations and fluxes in the Cuban conceptual radioactive waste repository are not higher than the natural values in the host rock. According to the application of new safety indicators, the reference disposal facility does not increase the natural activity concentration and fluxes in the environment. In order to implement these new safety indicator it has been used the current 226 Ra inventory of the Repository and the 226 Ra as natural concentration on the site. (authors)

  18. Failure analysis for ultrasound machines in a radiology department after implementation of predictive maintenance method

    Directory of Open Access Journals (Sweden)

    Greg Chu

    2018-01-01

    Full Text Available Objective: The objective of the study was to perform quantitative failure and fault analysis to the diagnostic ultrasound (US scanners in a radiology department after the implementation of the predictive maintenance (PdM method; to study the reduction trend of machine failure; to understand machine operating parameters affecting the failure; to further optimize the method to maximize the machine clinically service time. Materials and Methods: The PdM method has been implemented to the 5 US machines since 2013. Log books were used to record machine failures and their root causes together with the time spent on repair, all of which were retrieved, categorized, and analyzed for the period between 2013 and 2016. Results: There were a total of 108 cases of failure occurred in these 5 US machines during the 4-year study period. The average number of failure per month for all these machines was 2.4. Failure analysis showed that there were 33 cases (30.5% due to software, 44 cases (40.7% due to hardware, and 31 cases (28.7% due to US probe. There was a statistically significant negative correlation between the time spent on regular quality assurance (QA by hospital physicists with the time spent on faulty parts replacement over the study period (P = 0.007. However, there was no statistically significant correlation between regular QA time and total yearly breakdown case (P = 0.12, although there has been a decreasing trend observed in the yearly total breakdown. Conclusion: There has been a significant improvement on the machine failure of US machines attributed to the concerted effort of sonographers and physicists in our department to practice the PdM method, in that system component repair time has been reduced, and a decreasing trend in the number of system breakdown has been observed.

  19. Correlation of quantitative histopathological morphology and quantitative radiological analysis during aseptic loosening of hip endoprostheses.

    Science.gov (United States)

    Bertz, S; Kriegsmann, J; Eckardt, A; Delank, K-S; Drees, P; Hansen, T; Otto, M

    2006-01-01

    Aseptic hip prosthesis loosening is the most important long-term complication in total hip arthroplasty. Polyethylene (PE) wear is the dominant etiologic factor in aseptic loosening, which together with other factors induces mechanisms resulting in bone loss, and finally in implant loosening. The single-shot radiograph analysis (EBRA, abbreviation for the German term "Einzel-Bild-Röntgenanalyse") is a computerized method for early radiological prediction of aseptic loosening. In this study, EBRA parameters were correlated with histomorphological parameters of the periprosthetic membrane. Periprosthetic membranes obtained from 19 patients during revision surgery of loosened ABG I-type total hip pros-theses were analyzed histologically and morphometrically. The pre-existing EBRA parameters, the thickness of the PE debris lay-er and the dimension of inclination and anteversion, were compared with the density of macrophages and giant cells. Addi-tionally, the semiquantitatively determined density of lymphocytes, plasma cells, giant cells and the size of the necrotic areas were correlated with the EBRA results. All periprosthetic membranes were classified as debris-induced type membranes. We found a positive correlation between the number of giant cells and the thickness of the PE debris layer. There was no significant correlation between the number of macrophages or all semiquantitative parameters and EBRA parameters. The number of giant cells decreased with implant duration. The morphometrically measured number of foreign body giant cells more closely reflects the results of the EBRA. The semiquantitative estimation of giant cell density could not substitute for the morphometrical analysis. The density of macrophages, lymphocytes, plasma cells and the size of necrotic areas did not correlate with the EBRA parameters, indicating that there is no correlation with aseptic loosening.

  20. Radiology illustrated. Pediatric radiology

    Energy Technology Data Exchange (ETDEWEB)

    Kim, In-One (ed.) [Seoul National Univ. College of Medicine (Korea, Republic of). Dept. of Radiology

    2014-11-01

    Depicts characteristic imaging findings of common and uncommon diseases in the pediatric age group. Will serve as an ideal diagnostic reference in daily practice. Offers an excellent teaching aid, with numerous high-quality illustrations. This case-based atlas presents images depicting the findings typically observed when imaging a variety of common and uncommon diseases in the pediatric age group. The cases are organized according to anatomic region, covering disorders of the brain, spinal cord, head and neck, chest, cardiovascular system, gastrointestinal system, genitourinary system, and musculoskeletal system. Cases are presented in a form resembling teaching files, and the images are accompanied by concise informative text. The goal is to provide a diagnostic reference suitable for use in daily routine by both practicing radiologists and radiology residents or fellows. The atlas will also serve as a teaching aide and a study resource, and will offer pediatricians and surgeons guidance on the clinical applications of pediatric imaging.

  1. Federal support of radiological research

    International Nuclear Information System (INIS)

    Hendee, W.R.

    1981-01-01

    Pervading the plans and objective outlined herein for continued and enhanced federal support of research in radiology is a challenge of unparalleled magnitude, for the economic foundation on which this support is based has rarely been more precarious. The new administration in Washington may well be the most fiscally constrained in half a century, and its stated interest in reducing federal expenditures could have disastrous consequences for the scientific research effort in this country, including that in radiology and the radiological sciences. The circumvention of these consequences may well require the dedicated effort of the entire scientific community over the next few months and years, including that part representing radiology and the radiological sciences

  2. Analysis of uncertainties caused by the atmospheric dispersion model in accident consequence assessments with UFOMOD

    International Nuclear Information System (INIS)

    Fischer, F.; Ehrhardt, J.

    1988-06-01

    Various techniques available for uncertainty analysis of large computer models are applied, described and selected as most appropriate for analyzing the uncertainty in the predictions of accident consequence assessments. The investigation refers to the atmospheric dispersion and deposition submodel (straight-line Gaussian plume model) of UFOMOD, whose most important input variables and parameters are linked with probability distributions derived from expert judgement. Uncertainty bands show how much variability exists, sensitivity measures determine what causes this variability in consequences. Results are presented as confidence bounds of complementary cumulative frequency distributions (CCFDs) of activity concentrations, organ doses and health effects, partially as a function of distance from the site. In addition the ranked influence of the uncertain parameters on the different consequence types is shown. For the estimation of confidence bounds it was sufficient to choose a model parameter sample size of n (n=59) equal to 1.5 times the number of uncertain model parameters. Different samples or an increase of sample size did not change the 5%-95% - confidence bands. To get statistically stable results of the sensitivity analysis, larger sample sizes are needed (n=100, 200). Random or Latin-hypercube sampling schemes as tools for uncertainty and sensitivity analyses led to comparable results. (orig.) [de

  3. COMPARISON OF CONSEQUENCE ANALYSIS RESULTS FROM TWO METHODS OF PROCESSING SITE METEOROLOGICAL DATA

    International Nuclear Information System (INIS)

    , D

    2007-01-01

    Consequence analysis to support documented safety analysis requires the use of one or more years of representative meteorological data for atmospheric transport and dispersion calculations. At minimum, the needed meteorological data for most atmospheric transport and dispersion models consist of hourly samples of wind speed and atmospheric stability class. Atmospheric stability is inferred from measured and/or observed meteorological data. Several methods exist to convert measured and observed meteorological data into atmospheric stability class data. In this paper, one year of meteorological data from a western Department of Energy (DOE) site is processed to determine atmospheric stability class using two methods. The method that is prescribed by the U.S. Nuclear Regulatory Commission (NRC) for supporting licensing of nuclear power plants makes use of measurements of vertical temperature difference to determine atmospheric stability. Another method that is preferred by the U.S. Environmental Protection Agency (EPA) relies upon measurements of incoming solar radiation, vertical temperature gradient, and wind speed. Consequences are calculated and compared using the two sets of processed meteorological data from these two methods as input data into the MELCOR Accident Consequence Code System 2 (MACCS2) code

  4. Analysis of Patients' X-ray Exposure in 146 Percutaneous Radiologic Gastrostomies.

    Science.gov (United States)

    Petersen, Tim-Ole; Reinhardt, Martin; Fuchs, Jochen; Gosch, Dieter; Surov, Alexey; Stumpp, Patrick; Kahn, Thomas; Moche, Michael

    2017-09-01

    Purpose  Analysis of patient´s X-ray exposure during percutaneous radiologic gastrostomies (PRG) in a larger population. Materials and Methods  Data of primary successful PRG-procedures, performed between 2004 and 2015 in 146 patients, were analyzed regarding the exposition to X-ray. Dose-area-product (DAP), dose-length-product (DLP) respectively, and fluoroscopy time (FT) were correlated with the used x-ray systems (Flatpanel Detector (FD) vs. Image Itensifier (BV)) and the necessity for periprocedural placement of a nasogastric tube. Additionally, the effective X-ray dose for PRG placement using fluoroscopy (DL), computed tomography (CT), and cone beam CT (CBCT) was estimated using a conversion factor. Results  The median DFP of PRG-placements under fluoroscopy was 163 cGy*cm 2 (flat panel detector systems: 155 cGy*cm 2 ; X-ray image intensifier: 175 cGy*cm 2 ). The median DLZ was 2.2 min. Intraprocedural placement of a naso- or orogastric probe (n = 68) resulted in a significant prolongation of the median DLZ to 2.5 min versus 2 min in patients with an already existing probe. In addition, dose values were analyzed in smaller samples of patients in which the PRG was placed under CBCT (n = 7, median DFP = 2635 cGy*cm 2 ), or using CT (n = 4, median DLP = 657 mGy*cm). Estimates of the median DFP and DLP showed effective doses of 0.3 mSv for DL-assisted placements (flat panel detector 0.3 mSv, X-ray image converter 0.4 mSv), 7.9 mSv using a CBCT - flat detector, and 9.9 mSv using CT. This corresponds to a factor 26 of DL versus CBCT, or a factor 33 of DL versus CT. Conclusion  In order to minimize X-ray exposure during PRG-procedures for patients and staff, fluoroscopically-guided interventions should employ flat detector systems with short transmittance sequences in low dose mode and with slow image frequency. Series recordings can be dispensed with. The intraprocedural placement of a naso- or orogastric probe

  5. Radiological functional analysis of the vascular system contrast media, methods, results

    CERN Document Server

    1983-01-01

    Scientists and engineers have been involved in medical radiology from the very beginning. At times advances in this field occur at a tremen­ dously fast pace. Developments in radiological diagnostics have - technologically and medically speaking - focused on morphology. At present, computer-aided tomography (CAT) is at a high point in deve1opment, medical application, and validation. The preconditions for this success were rapid advances in electronics and computer technology - in hardware and in software - and an unexpected cost reduction in these fields; the co operation of various scientific disci­ plines was also essential. Functional radiological diagnosis has been neglected in part, owing to the emphasis on morphology, but alone the synthesis of morphology and function prornises further advances. Apart from the limited capabilities ofuItrasonic techniques there is no way other than using X-rays to carry out functional studies of organs and their systems through an intact body surface. It is frequently...

  6. Radiologically assisted percutaneous gastrostomy or enterostomy. A retrospective analysis of 90 procedures

    International Nuclear Information System (INIS)

    Mildenberger, P.; Oberholzer, K.; Kauczor, H.U.; Dueber, C.; Kurz, S.; Schild, H.; Thelen, M.

    1996-01-01

    To analyse retrospectively the indications, technique and results of radiologically induced gastrostomies or enterostomies. Radiologically assisted gastrostomies or enterostomies were induced in 90 patients, mostly with high grade obstructions due to head and neck tumours or oesophageal tumours. 19/90 patients had had previous resection of the oesophagus or gastric operations. A catheter was successfully introduced in all patients. In 11/90 patients this was followed by a two-stage procedure. In 16/90 patients puncture was performed under CT control because of some anatomical peculiarity. Serious complication occurred in 9/90 patients but in only one was surgery necessary. There were no deaths resulting from the procedure but mortality after 30 days was 6.7%. Radiologically assisted gastrostomies or enterostomies are a reliable and effective form of treatment even amongst difficult patients. The results and complications are comparable to those from endoscopic procedures. (orig.) [de

  7. Analysis of Low Appropriateness Score Exam Trends in Decision Support-based Radiology Order Entry System.

    Science.gov (United States)

    Gupta, Supriya; Klein, Kandace; Singh, Anand H; Thrall, James H

    2017-05-01

    Awareness of imaging utilization increased after implementation of Radiology Order Entry with decision support systems (ROE-DS). Our hypothesis is few exams with low Clinical Appropriateness Score (CAS) on ROE-DS are performed. Clinical indications of exams with CAS less than 3 (9-point scale) were re-reviewed and reports analyzed. Structured Query Language-based query retrieved exams with CAS less than 3 in ROE-DS from January 2007 to December 2011. Reasons provided by physicians for ordering these exams and reports of exams performed were analyzed. For each indication, number of exams ordered and performed was calculated. Statistical significance was assessed using Student's t test and χ 2 analysis (P < .05). From 445,984 exams, 12,615 exams (2.8%) had CAS less than 3, and 7,956 exams (63%) were performed. Reasons for ordering of 12,615 low CAS exams were as follows: Requests by physician specialists without further explanation (4,516 = 35.8%), notation of special clinical circumstances (2,877 = 22.8%), requests by nonphysician staff without further explanation (1,383 = 10.9%), absence of suspected finding on previous modality (1,099 = 8.7%), patient preference (737 = 5.8%), and requests based on radiologists' recommendations (706 = 5.6%). Difference between male and female (male < female) preferences for low CAS exams was statistically significant (P < .01). Imaging outcome was highest for extremity MRI cases (66.7%; P < .01). Less than 3% of exams ordered had low CAS and about two-thirds of these were performed. Most common indication for ordering these exams was physician specialist request based on opinion of medical necessity without specification. Extremity MRI constituted the highest positive findings for low CAS exams performed. Published by Elsevier Inc.

  8. A Consequence Analysis of the Explosion of Spherical Tanks Containing Liquefied Petroleum Gas (LPG

    Directory of Open Access Journals (Sweden)

    Hadi Zareei

    2016-07-01

    Full Text Available A consequence analysis was performed in one of the gas refineries in Iran to investigate the risks andpotential losses resulted from accidents. Specifically, the consequences of an explosion in LPGspherical tanks were modeled using PHAST and MATLAB software. In this paper, three methods ofcalculation of PHAST software TNT, multi-energy, and BST were used. The results showed thatmulti energy method is the best method to evaluate overpressure. It was 0.150 bar and 0.159 bar in adistance of 1000 m far from the blast using PHAST and MATLAB respectively. This overpressurecan damage a wall with 30 cm thickness. It also affects the human threshold (1% ruptured eardrum.Finally, it was found that 100% lethality in a minute happened at 285.5 m and 37.5 kW/m2 when theexplosion happened.

  9. Endobronchial valves in severe emphysematous patients: CT evaluation of lung fissures completeness, treatment radiological response and quantitative emphysema analysis

    Energy Technology Data Exchange (ETDEWEB)

    Koenigkam-Santos, Marcel, E-mail: marcelk46@yahoo.com.br, E-mail: marcelk46@usp.b [Universidade de Sao Paulo (HCFMRP/USP), Ribeirao Preto, SP (Brazil). Hospital das Clinicas da Faculdade de Medicina; Paula, Wagner Diniz de [University of Brasilia (UnB), DF (Brazil). Brasilia University Hospital; Gompelmann, Daniela [University of Heidelberg (Germany). Department of Pneumology and Respiratory Medicine of the Chest Clinic (Thoraxklinik); Kauczor, Hans-Ulrich [University of Heidelberg (Germany). Department of Diagnostic and Interventional Radiology; Heussel, Claus Peter; Puderbach, Michael [University of Heidelberg (Germany). Department of Diagnostic and Interventional Radiology with Nuclear Medicine of the Chest Clinic (Thoraxklinik)

    2013-01-15

    Objective: To evaluate lung fissures completeness, post-treatment radiological response and quantitative CT analysis (QCTA) in a population of severe emphysematous patients submitted to endobronchial valves (EBV) implantation. Materials and Methods: Multi-detectors CT exams of 29 patients were studied, using thin-section low dose protocol without contrast. Two radiologists retrospectively reviewed all images in consensus; fissures completeness was estimated in 5% increments and post-EBV radiological response (target lobe atelectasis/volume loss) was evaluated. QCTA was performed in pre and post-treatment scans using a fully automated software. Results: CT response was present in 16/29 patients. In the negative CT response group, all 13 patients presented incomplete fissures, and mean oblique fissures completeness was 72.8%, against 88.3% in the other group. QCTA most significant results showed a reduced post-treatment total lung volume (LV) (mean 542 ml), reduced EBV-submitted LV (700 ml) and reduced emphysema volume (331.4 ml) in the positive response group, which also showed improved functional tests. Conclusion: EBV benefit is most likely in patients who have complete interlobar fissures and develop lobar atelectasis. In patients with no radiological response we observed a higher prevalence of incomplete fissures and a greater degree of incompleteness. The fully automated QCTA detected the post-treatment alterations, especially in the treated lung analysis. (author)

  10. Analysis of heavy radiological accidents in NPP and gamma-irradiators

    International Nuclear Information System (INIS)

    Angelov, V.; Semova, T.; Bonchev, Ts.

    1995-01-01

    A review of several heavy radiological accidents, their cause, character, radioactivity emission, victims and economical impact is presented in the form of uniform tables. Eleven cases of incidents in power plants and 4 cases of accidents involving powerful gamma irradiators are considered. Radiological accidents in Bulgaria, not connected with the Kozloduy NPP, are listed. The human factor has been identified as the main cause for most of the accidents. It is stressed that the probability of heavy accident increases at the time of reactor refuelling, repair or testing. Technical failures could be eliminated by improved check and diagnostics procedures. 2 tabs., 12 refs

  11. Analysis of heavy radiological accidents in NPP and gamma-irradiators

    Energy Technology Data Exchange (ETDEWEB)

    Angelov, V [Civil Defence Administration, Sofia (Bulgaria); Semova, T; Bonchev, Ts [Sofia Univ. (Bulgaria). Fizicheski Fakultet

    1996-12-31

    A review of several heavy radiological accidents, their cause, character, radioactivity emission, victims and economical impact is presented in the form of uniform tables. Eleven cases of incidents in power plants and 4 cases of accidents involving powerful gamma irradiators are considered. Radiological accidents in Bulgaria, not connected with the Kozloduy NPP, are listed. The human factor has been identified as the main cause for most of the accidents. It is stressed that the probability of heavy accident increases at the time of reactor refuelling, repair or testing. Technical failures could be eliminated by improved check and diagnostics procedures. 2 tabs., 12 refs.

  12. Probabilistic accident consequence uncertainty analysis: Dispersion and deposition uncertainty assessment, appendices A and B

    International Nuclear Information System (INIS)

    Harper, F.T.; Young, M.L.; Miller, L.A.; Hora, S.C.; Lui, C.H.; Goossens, L.H.J.; Cooke, R.M.; Paesler-Sauer, J.; Helton, J.C.

    1995-01-01

    The development of two new probabilistic accident consequence codes, MACCS and COSYMA, completed in 1990, estimate the risks presented by nuclear installations based on postulated frequencies and magnitudes of potential accidents. In 1991, the US Nuclear Regulatory Commission (NRC) and the Commission of the European Communities (CEC) began a joint uncertainty analysis of the two codes. The objective was to develop credible and traceable uncertainty distributions for the input variables of the codes. Expert elicitation, developed independently, was identified as the best technology available for developing a library of uncertainty distributions for the selected consequence parameters. The study was formulated jointly and was limited to the current code models and to physical quantities that could be measured in experiments. To validate the distributions generated for the wet deposition input variables, samples were taken from these distributions and propagated through the wet deposition code model along with the Gaussian plume model (GPM) implemented in the MACCS and COSYMA codes. Resulting distributions closely replicated the aggregated elicited wet deposition distributions. Project teams from the NRC and CEC cooperated successfully to develop and implement a unified process for the elaboration of uncertainty distributions on consequence code input parameters. Formal expert judgment elicitation proved valuable for synthesizing the best available information. Distributions on measurable atmospheric dispersion and deposition parameters were successfully elicited from experts involved in the many phenomenological areas of consequence analysis. This volume is the second of a three-volume document describing the project and contains two appendices describing the rationales for the dispersion and deposition data along with short biographies of the 16 experts who participated in the project

  13. Probabilistic accident consequence uncertainty analysis: Dispersion and deposition uncertainty assessment, main report

    International Nuclear Information System (INIS)

    Harper, F.T.; Young, M.L.; Miller, L.A.; Hora, S.C.; Lui, C.H.; Goossens, L.H.J.; Cooke, R.M.; Paesler-Sauer, J.; Helton, J.C.

    1995-01-01

    The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in 1990. These codes estimate the risks presented by nuclear installations based on postulated frequencies and magnitudes of potential accidents. In 1991, the US Nuclear Regulatory Commission (NRC) and the Commission of the European Communities (CEC) began a joint uncertainty analysis of the two codes. The ultimate objective of the joint effort was to develop credible and traceable uncertainty distributions for the input variables of the codes. Expert elicitation was identified as the best technology available for developing a library of uncertainty distributions for the selected consequence parameters. The study was formulated jointly and was limited to the current code models and to physical quantities that could be measured in experiments. Experts developed their distributions independently. To validate the distributions generated for the wet deposition input variables, samples were taken from these distributions and propagated through the wet deposition code model. Resulting distributions closely replicated the aggregated elicited wet deposition distributions. To validate the distributions generated for the dispersion code input variables, samples from the distributions and propagated through the Gaussian plume model (GPM) implemented in the MACCS and COSYMA codes. Project teams from the NRC and CEC cooperated successfully to develop and implement a unified process for the elaboration of uncertainty distributions on consequence code input parameters. Formal expert judgment elicitation proved valuable for synthesizing the best available information. Distributions on measurable atmospheric dispersion and deposition parameters were successfully elicited from experts involved in the many phenomenological areas of consequence analysis. This volume is the first of a three-volume document describing the project

  14. Probabilistic accident consequence uncertainty analysis: Dispersion and deposition uncertainty assessment, appendices A and B

    Energy Technology Data Exchange (ETDEWEB)

    Harper, F.T.; Young, M.L.; Miller, L.A. [Sandia National Labs., Albuquerque, NM (United States); Hora, S.C. [Univ. of Hawaii, Hilo, HI (United States); Lui, C.H. [Nuclear Regulatory Commission, Washington, DC (United States); Goossens, L.H.J.; Cooke, R.M. [Delft Univ. of Technology (Netherlands); Paesler-Sauer, J. [Research Center, Karlsruhe (Germany); Helton, J.C. [and others

    1995-01-01

    The development of two new probabilistic accident consequence codes, MACCS and COSYMA, completed in 1990, estimate the risks presented by nuclear installations based on postulated frequencies and magnitudes of potential accidents. In 1991, the US Nuclear Regulatory Commission (NRC) and the Commission of the European Communities (CEC) began a joint uncertainty analysis of the two codes. The objective was to develop credible and traceable uncertainty distributions for the input variables of the codes. Expert elicitation, developed independently, was identified as the best technology available for developing a library of uncertainty distributions for the selected consequence parameters. The study was formulated jointly and was limited to the current code models and to physical quantities that could be measured in experiments. To validate the distributions generated for the wet deposition input variables, samples were taken from these distributions and propagated through the wet deposition code model along with the Gaussian plume model (GPM) implemented in the MACCS and COSYMA codes. Resulting distributions closely replicated the aggregated elicited wet deposition distributions. Project teams from the NRC and CEC cooperated successfully to develop and implement a unified process for the elaboration of uncertainty distributions on consequence code input parameters. Formal expert judgment elicitation proved valuable for synthesizing the best available information. Distributions on measurable atmospheric dispersion and deposition parameters were successfully elicited from experts involved in the many phenomenological areas of consequence analysis. This volume is the second of a three-volume document describing the project and contains two appendices describing the rationales for the dispersion and deposition data along with short biographies of the 16 experts who participated in the project.

  15. Imaging and radiology

    Science.gov (United States)

    Interventional radiology; Diagnostic radiology; X-ray imaging ... DIAGNOSTIC RADIOLOGY Diagnostic radiology helps health care professionals see structures inside your body. Doctors that specialize in the interpretation ...

  16. Chronicle of pediatric radiology

    International Nuclear Information System (INIS)

    Benz-Bohm, Gabriele; Richter, Ernst

    2012-01-01

    The chronicle of pediatric radiology covers the following issues: Development of pediatric radiology in Germany (BRD, DDR, pediatric radiological accommodations); development of pediatric radiology in the Netherlands (chronology and pediatric radiological accommodations); development of pediatric radiology in Austria (chronology and pediatric radiological accommodations); development of pediatric radiology in Switzerland (chronology and pediatric radiological accommodations).

  17. 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.)

  18. 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.)

  19. Design basis event consequence analyses for the Yucca Mountain project

    International Nuclear Information System (INIS)

    Orvis, D.D.; Haas, M.N.; Martin, J.H.

    1997-01-01

    Design basis event (DBE) definition and analysis is an ongoing and integrated activity among the design and analysis groups of the Yucca Mountain Project (YMP). DBE's are those that potentially lead to breach of the waste package and waste form (e.g., spent fuel rods) with consequent release of radionuclides to the environment. A Preliminary Hazards Analysis (PHA) provided a systematic screening of external and internal events that were candidate DBE's that will be subjected to analyses for radiological consequences. As preparation, pilot consequence analyses for the repository subsurface and surface facilities have been performed to define the methodology, data requirements, and applicable regulatory limits

  20. Health literacy in vascular and interventional radiology: a comparative analysis of online patient education resources.

    Science.gov (United States)

    Hansberry, David R; Kraus, Carl; Agarwal, Nitin; Baker, Stephen R; Gonzales, Sharon F

    2014-08-01

    The Internet is frequently accessed by patients as a resource for medical knowledge. However, the provided material is typically written at a level well above the recommended 7th grade level. A clear understanding of the capabilities, limitations, risks, and benefits of interventional radiology by patients, both current and prospective, is hindered when the textual information offered to the public is pitched at a level of sophistication too high for general comprehension. In January 2013, all 25 patient education resources from the Cardiovascular and Interventional Radiology Society of Europe (CIRSE) Web site ( http://www.cirse.org ) and all 31 resources from the Society of Interventional Radiology (SIR) Web site ( http://www.sirweb.org ) were analyzed for their specific level of readability using ten quantitative scales: Flesch Reading Ease, Flesch-Kincaid Grade Level, Simple Measure of Gobbledygook, Gunning fog index, New Fog Count, Coleman-Liau index, FORCAST formula, Fry graph, Raygor Readability Estimate, and New Dale-Chall. Collectively, the patient education resources on the CIRSE Web site are written at the 12.3 grade level, while the resources on the SIR Web site are written at the 14.5 grade level. Educational health care materials available on both the CIRSE and the SIR Web sites are presented in language in the aggregate that could be too difficult for many lay people to fully understand. Given the complex nature of vascular and interventional radiology, it may be advantageous to rewrite these educational resources at a lower reading level to increase comprehension.

  1. The most downloaded and most cited articles in radiology journals: a comparative bibliometric analysis.

    Science.gov (United States)

    Baek, Sora; Yoon, Dae Young; Lim, Kyoung Ja; Cho, Young Kwon; Seo, Young Lan; Yun, Eun Joo

    2018-05-07

    To evaluate and compare the characteristics of the most downloaded and most cited articles in radiology journals. We selected 41 radiology journals that provided lists of both the most downloaded and most cited articles on their websites, and identified the 596 most downloaded articles and 596 most cited articles. We compared the following characteristics of the most downloaded and most cited articles: year of publication, journal title, department of the first author, country of origin, publication type, radiologic subspecialty, radiologic technique and accessibility. Compared to the most cited articles, the most downloaded articles were more frequently review articles (36.1% vs 17.1%, p articles, the most downloaded articles more frequently originated from the UK (8.7% vs 5.0%, p articles (46.0% vs 39.4%, p articles are more frequent among the most downloaded articles. • There was only small overlap between the most downloaded and most cited articles. • Educational articles were more frequent among the most downloaded articles. • Free-access articles are more frequent among the most downloaded articles.

  2. Analysis of radiological examination request forms in conjunction with justification of X-ray exposures

    International Nuclear Information System (INIS)

    Triantopoulou, Ch.; Tsalafoutas, I.; Maniatis, P.; Papavdis, D.; Raios, G.; Siafas, I.; Velonakis, S.; Koulentianos, E.

    2005-01-01

    Objectives: To evaluate the adequacy of patient data and clinical information transmitted to the radiological departments by the referring clinicians in view of the justification demands concerning the radiological examinations, as those are described in the Radiation Protection Regulations of the European Union Nations. Materials and methods: Request forms for 1708 patients referred to radiology department and 410 referred to the CT department were evaluated concerning the proper completion of the form fields. Furthermore, for CT examinations a more detailed evaluation was carried out, to assess the rationalistic use of CT within the diagnostic algorithm. Results: Not properly completed request forms to both departments were observed, however, the omissions were more prominent for the referrals to the radiology department, where the age and the probable clinical diagnosis was not given in 81.5 and 46% of the forms, respectively. Furthermore, the emergency indication was less cautiously used compared to the CT requests. For the CT department 33.3% of requests were justified and the final diagnosis was included in the referring doctor's probable clinical diagnosis. U/S was the examination of choice in 51% of the cases where an examination should have been performed before CT and in 70.6% of the cases where an alternative examination was proposed. Conclusions: The inadequate transmission of clinical information and the large number of not fully justified CT requests observed in this study are typical examples of the various problems that radiologists have to face in order to apply the justification directives

  3. Wrong decisions in radiology. Analysis of causes and strategies for error prevention

    International Nuclear Information System (INIS)

    Lackner, Klaus-Juergen; Krug, Kathrin Barbara

    2009-01-01

    The book covers observations on errors concerning radiological decisions within a ten-year period. The compiled information is supposed to prevent similar errors in the future. The case studies cover the following issues: cranium, thorax, mamma, abdomen (liver, pancreas, colon), (gastrointestinal tract, urogenital tract), spinal cord, skeleton and blood vessels.

  4. Occupational Analysis: Hospital Radiologic Technologist. The UCLA Allied Health Professions Project.

    Science.gov (United States)

    Reeder, Glenn D.; And Others

    In an effort to meet the growing demand for skilled radiologic technologists and other supportive personnel educated through the associate degree level, a national survey was conducted as part of the UCLA Allied Health Professions Project to determine the tasks performed by personnel in the field and lay the groundwork for development of…

  5. Analysis of conditions to safety and radiological protection of Brazilian research particle accelerators facilities

    International Nuclear Information System (INIS)

    Lourenco, Manuel Jacinto Martins

    2010-01-01

    Eleven institutions of education and research in Brazil use particle accelerators, which fulfill different functions and activities. Currently, these institutions employ a total of fifteen accelerators. In this paper, the object of study is the radiological protection of occupationally exposed individuals, the general public and the radiation safety of particle accelerators. Research facilities with accelerators are classified in categories I and II according to the International Atomic Energy Agency or groups IX and X in accordance with the Brazilian National Commission of Nuclear Energy. Of the 15 accelerators in use for research in Brazil, four belong to category I or group X and eleven belong to category II or group IX. The methodology presented and developed in this work was made through the inspection and assessment of safety and radiological protection of thirteen particle accelerators facilities, and its main purpose was to promote safer use of this practice by following established guidelines for safety and radiological protection. The results presented in this work showed the need to create a program, in our country, for the control of safety and radiological protection of this ionizing radiation practice. (author)

  6. Radiologic protection in dental radiology

    International Nuclear Information System (INIS)

    Pacheco Jimenez, R.E.; Bermudez Jimenez, L.A.

    2000-01-01

    With this work and employing the radioprotection criterion, the authors pretend to minimize the risks associated to this practice; without losing the quality of the radiologic image. Odontology should perform the following criterions: 1. Justification: all operation of practice that implies exposition to radiations, should be reweighed, through an analysis of risks versus benefits, with the purpose to assure, that the total detriment will be small, compared to resultant benefit of this activity. 2. Optimization: all of the exposures should be maintained as low as reasonable possible, considering the social and economic factors. 3. Dose limit: any dose limit system should be considered as a top condition, nota as an admissible level. (S. Grainger)

  7. Source term derivation and radiological safety analysis for the TRICO II research reactor in Kinshasa

    International Nuclear Information System (INIS)

    Muswema, J.L.; Ekoko, G.B.; Lukanda, V.M.; Lobo, J.K.-K.; Darko, E.O.; Boafo, E.K.

    2015-01-01

    Highlights: • Atmospheric dispersion modeling for two credible accidents of the TRIGA Mark II research reactor in Kinshasa (TRICO II) was performed. • Radiological safety analysis after the postulated initiating events (PIE) was also carried out. • The Karlsruhe KORIGEN and the HotSpot Health Physics codes were used to achieve the objectives of this study. • All the values of effective dose obtained following the accident scenarios were below the regulatory limits for reactor staff members and the public, respectively. - Abstract: The source term from the 1 MW TRIGA Mark II research reactor core of the Democratic Republic of the Congo was derived in this study. An atmospheric dispersion modeling followed by radiation dose calculation were performed based on two possible postulated accident scenarios. This derivation was made from an inventory of peak radioisotope activities released in the core by using the Karlsruhe version of isotope generation code KORIGEN. The atmospheric dispersion modeling was performed with HotSpot code, and its application yielded to radiation dose profile around the site using meteorological parameters specific to the area under study. The two accident scenarios were picked from possible accident analyses for TRIGA and TRIGA-fueled reactors, involving the case of destruction of the fuel element with highest activity release and a plane crash on the reactor building as the worst case scenario. Deterministic effects of these scenarios are used to update the Safety Analysis Report (SAR) of the reactor, and for its current version, these scenarios are not yet incorporated. Site-specific meteorological conditions were collected from two meteorological stations: one installed within the Atomic Energy Commission and another at the National Meteorological Agency (METTELSAT), which is not far from the site. Results show that in both accident scenarios, radiation doses remain within the limits, far below the recommended maximum effective

  8. Source term derivation and radiological safety analysis for the TRICO II research reactor in Kinshasa

    Energy Technology Data Exchange (ETDEWEB)

    Muswema, J.L., E-mail: jeremie.muswem@unikin.ac.cd [Faculty of Science, University of Kinshasa, P.O. Box 190, KIN XI (Congo, The Democratic Republic of the); Ekoko, G.B. [Faculty of Science, University of Kinshasa, P.O. Box 190, KIN XI (Congo, The Democratic Republic of the); Lukanda, V.M. [Faculty of Science, University of Kinshasa, P.O. Box 190, KIN XI (Congo, The Democratic Republic of the); Democratic Republic of the Congo' s General Atomic Energy Commission, P.O. Box AE1 (Congo, The Democratic Republic of the); Lobo, J.K.-K. [Faculty of Science, University of Kinshasa, P.O. Box 190, KIN XI (Congo, The Democratic Republic of the); Darko, E.O. [Radiation Protection Institute, Ghana Atomic Energy Commission, P.O. Box LG 80, Legon, Accra (Ghana); Boafo, E.K. [University of Ontario Institute of Technology, 2000 Simcoe St. North, Oshawa, ONL1 H7K4 (Canada)

    2015-01-15

    Highlights: • Atmospheric dispersion modeling for two credible accidents of the TRIGA Mark II research reactor in Kinshasa (TRICO II) was performed. • Radiological safety analysis after the postulated initiating events (PIE) was also carried out. • The Karlsruhe KORIGEN and the HotSpot Health Physics codes were used to achieve the objectives of this study. • All the values of effective dose obtained following the accident scenarios were below the regulatory limits for reactor staff members and the public, respectively. - Abstract: The source term from the 1 MW TRIGA Mark II research reactor core of the Democratic Republic of the Congo was derived in this study. An atmospheric dispersion modeling followed by radiation dose calculation were performed based on two possible postulated accident scenarios. This derivation was made from an inventory of peak radioisotope activities released in the core by using the Karlsruhe version of isotope generation code KORIGEN. The atmospheric dispersion modeling was performed with HotSpot code, and its application yielded to radiation dose profile around the site using meteorological parameters specific to the area under study. The two accident scenarios were picked from possible accident analyses for TRIGA and TRIGA-fueled reactors, involving the case of destruction of the fuel element with highest activity release and a plane crash on the reactor building as the worst case scenario. Deterministic effects of these scenarios are used to update the Safety Analysis Report (SAR) of the reactor, and for its current version, these scenarios are not yet incorporated. Site-specific meteorological conditions were collected from two meteorological stations: one installed within the Atomic Energy Commission and another at the National Meteorological Agency (METTELSAT), which is not far from the site. Results show that in both accident scenarios, radiation doses remain within the limits, far below the recommended maximum effective

  9. Analysis of nuclear and radiological events. Textbook for lecture in graduate school of engineering in the University of Tokyo

    International Nuclear Information System (INIS)

    Watanabe, Norio

    2007-02-01

    The Japan Atomic Energy Agency is carrying out the cooperative activity by providing specialized educational and training staff and making our facilities available for the graduate school of engineering in The University of Tokyo as part of developing human resources in nuclear technology. This report is prepared as a textbook for the lecture in the graduate school of engineering in The University of Tokyo and provides the outlines of activities on the analysis of nuclear and radiological events and analysis methods as well as the summaries of major incidents and accidents that occurred. (author)

  10. [Controlling instruments in radiology].

    Science.gov (United States)

    Maurer, M

    2013-10-01

    Due to the rising costs and competitive pressures radiological clinics and practices are now facing, controlling instruments are gaining importance in the optimization of structures and processes of the various diagnostic examinations and interventional procedures. It will be shown how the use of selected controlling instruments can secure and improve the performance of radiological facilities. A definition of the concept of controlling will be provided. It will be shown which controlling instruments can be applied in radiological departments and practices. As an example, two of the controlling instruments, material cost analysis and benchmarking, will be illustrated.

  11. Uncertainty and sensitivity analysis of early exposure results with the MACCS Reactor Accident Consequence Model

    International Nuclear Information System (INIS)

    Helton, J.C.; Johnson, J.D.; McKay, M.D.; Shiver, A.W.; Sprung, J.L.

    1995-01-01

    Uncertainty and sensitivity analysis techniques based on Latin hypercube sampling, partial correlation analysis and stepwise regression analysis are used in an investigation with the MACCS model of the early health effects associated with a severe accident at a nuclear power station. The primary purpose of this study is to provide guidance on the variables to be considered in future review work to reduce the uncertainty in the important variables used in the calculation of reactor accident consequences. The effects of 34 imprecisely known input variables on the following reactor accident consequences are studied: number of early fatalities, number of cases of prodromal vomiting, population dose within 10 mi of the reactor, population dose within 1000 mi of the reactor, individual early fatality probability within 1 mi of the reactor, and maximum early fatality distance. When the predicted variables are considered collectively, the following input variables were found to be the dominant contributors to uncertainty: scaling factor for horizontal dispersion, dry deposition velocity, inhalation protection factor for nonevacuees, groundshine shielding factor for nonevacuees, early fatality hazard function alpha value for bone marrow exposure, and scaling factor for vertical dispersion

  12. Gastrointestinal transit after transverse colostomy: study of solid radiopaque markers progression and others clinical and radiological events - analysis of 20 cases

    International Nuclear Information System (INIS)

    Deutsch, Claudio Roberto

    1988-01-01

    The gastrointestinal transit was studied in 20 patients with loop transverse colostomies and previously normal colons. This analysis was performed through radiological observation of progression of 20 radiopaque pellets and measurements of its transit time in the various segments of the digestive tract. An evaluation of other related clinical and radiological events was carried out sentimentality's. In order to better understand the influence of the surgical procedure, the study was performed under similar dietary and supportive care conditions and standard radiological studies before and after the re-establishment of transit, thus enabling a comparison with the same individual. (author)

  13. Dental radiology

    International Nuclear Information System (INIS)

    Bhaskar, S.N.

    1982-01-01

    The book presents the radiological manifestations of the maxillodental region in a suitable manner for fast detection and correct diagnosing of diseases of the teeth, soft tissue, and jaws. Classification therefore is made according to the radiological manifestations of the diseases and not according to etiology. (orig./MG) [de

  14. Analysis of papers in the journal of Korean radiologic society of recent three years with special emphasis on citation index

    International Nuclear Information System (INIS)

    Yang, Seoung Oh; Choi, Sang Hee; Jeong, Cheol Hwe; Lee, Yung Il

    1990-01-01

    The papers in the Journal of the Korean Radiologic Society (JKRS) during recent three years were surveyed by analysis of their types, topics, organs, employed modalities, and cited literatures. Citation analysis is a method of studying interrelationships between papers and journals, and the most important application of citation analysis is in studies of science policy and research evaluation to evaluate the implementation of science policy and to monitor research performance. Using these citation analysis to map the journal communications network may indicate to more efficient scientific progress. Total number of papers published by JKRS for recent 3 years was 473 papers (Clinical : 354, Case report : 91, Experimental : 26, Educational : 2). The most common organ system of the papers was abdomen (head and neck, chest, musculoskeletal, cardiovascular, and urologic system in the order of decreasing frequency). The most popular topic was techniques including newer modalities and interventional radiology, and normal measurement, tuberculosis, hepatoma, normal anatomy and the like followed. Total number of cited references was 8,642 (18.26 per one paper), and the average number of authors per paper was 4.83. The most frequently used modality was CT (41%) followed by simple radiography, ultrasonogram, fluoroscopic study, angiography, nuclear imaging, and MRI. Using this kind of analysis as a guide for writing a paper for the JKRS, it could be well-organized and uplifted in its format and contents

  15. Sensitivity Analysis of Weather Variables on Offsite Consequence Analysis Tools in South Korea and the United States.

    Science.gov (United States)

    Kim, Min-Uk; Moon, Kyong Whan; Sohn, Jong-Ryeul; Byeon, Sang-Hoon

    2018-05-18

    We studied sensitive weather variables for consequence analysis, in the case of chemical leaks on the user side of offsite consequence analysis (OCA) tools. We used OCA tools Korea Offsite Risk Assessment (KORA) and Areal Location of Hazardous Atmospheres (ALOHA) in South Korea and the United States, respectively. The chemicals used for this analysis were 28% ammonia (NH₃), 35% hydrogen chloride (HCl), 50% hydrofluoric acid (HF), and 69% nitric acid (HNO₃). The accident scenarios were based on leakage accidents in storage tanks. The weather variables were air temperature, wind speed, humidity, and atmospheric stability. Sensitivity analysis was performed using the Statistical Package for the Social Sciences (SPSS) program for dummy regression analysis. Sensitivity analysis showed that impact distance was not sensitive to humidity. Impact distance was most sensitive to atmospheric stability, and was also more sensitive to air temperature than wind speed, according to both the KORA and ALOHA tools. Moreover, the weather variables were more sensitive in rural conditions than in urban conditions, with the ALOHA tool being more influenced by weather variables than the KORA tool. Therefore, if using the ALOHA tool instead of the KORA tool in rural conditions, users should be careful not to cause any differences in impact distance due to input errors of weather variables, with the most sensitive one being atmospheric stability.

  16. Sensitivity Analysis of Weather Variables on Offsite Consequence Analysis Tools in South Korea and the United States

    Directory of Open Access Journals (Sweden)

    Min-Uk Kim

    2018-05-01

    Full Text Available We studied sensitive weather variables for consequence analysis, in the case of chemical leaks on the user side of offsite consequence analysis (OCA tools. We used OCA tools Korea Offsite Risk Assessment (KORA and Areal Location of Hazardous Atmospheres (ALOHA in South Korea and the United States, respectively. The chemicals used for this analysis were 28% ammonia (NH3, 35% hydrogen chloride (HCl, 50% hydrofluoric acid (HF, and 69% nitric acid (HNO3. The accident scenarios were based on leakage accidents in storage tanks. The weather variables were air temperature, wind speed, humidity, and atmospheric stability. Sensitivity analysis was performed using the Statistical Package for the Social Sciences (SPSS program for dummy regression analysis. Sensitivity analysis showed that impact distance was not sensitive to humidity. Impact distance was most sensitive to atmospheric stability, and was also more sensitive to air temperature than wind speed, according to both the KORA and ALOHA tools. Moreover, the weather variables were more sensitive in rural conditions than in urban conditions, with the ALOHA tool being more influenced by weather variables than the KORA tool. Therefore, if using the ALOHA tool instead of the KORA tool in rural conditions, users should be careful not to cause any differences in impact distance due to input errors of weather variables, with the most sensitive one being atmospheric stability.

  17. Handbook of radiologic procedures

    International Nuclear Information System (INIS)

    Hedgcock, M.

    1986-01-01

    This book is organized around radiologic procedures with each discussed from the points of view of: indications, contraindications, materials, method of procedures and complications. Covered in this book are: emergency radiology chest radiology, bone radiology, gastrointestinal radiology, GU radiology, pediatric radiology, computerized tomography, neuroradiology, visceral and peripheral angiography, cardiovascular radiology, nuclear medicine, lymphangiography, and mammography

  18. Quantitative analysis of the level of readability of online emergency radiology-based patient education resources.

    Science.gov (United States)

    Hansberry, David R; D'Angelo, Michael; White, Michael D; Prabhu, Arpan V; Cox, Mougnyan; Agarwal, Nitin; Deshmukh, Sandeep

    2018-04-01

    The vast amount of information found on the internet, combined with its accessibility, makes it a widely utilized resource for Americans to find information pertaining to medical information. The field of radiology is no exception. In this paper, we assess the readability level of websites pertaining specifically to emergency radiology. Using Google, 23 terms were searched, and the top 10 results were recorded. Each link was evaluated for its readability level using a set of ten reputable readability scales. The search terms included the following: abdominal ultrasound, abdominal aortic aneurysm, aortic dissection, appendicitis, cord compression, CT abdomen, cholecystitis, CT chest, diverticulitis, ectopic pregnancy, epidural hematoma, dural venous thrombosis, head CT, MRI brain, MR angiography, MRI spine, ovarian torsion, pancreatitis, pelvic ultrasound, pneumoperitoneum, pulmonary embolism, subarachnoid hemorrhage, and subdural hematoma. Any content that was not written for patients was excluded. The 230 articles that were assessed were written, on average, at a 12.1 grade level. Only 2 of the 230 articles (1%) were written at the third to seventh grade recommended reading level set forth by the National Institutes of Health (NIH) and American Medical Association (AMA). Fifty-two percent of the 230 articles were written so as to require a minimum of a high school education (at least a 12th grade level). Additionally, 17 of the 230 articles (7.3%) were written at a level that exceeded an undergraduate education (at least a 16th grade level). The majority of websites with emergency radiology-related patient education materials are not adhering to the NIH and AMA's recommended reading levels, and it is likely that the average reader is not benefiting fully from these information outlets. With the link between health literacy and poor health outcomes, it is important to address the online content in this area of radiology, allowing for patient to more fully benefit

  19. Acute traumatic central cord syndrome: analysis of clinical and radiological correlations.

    Science.gov (United States)

    Miranda, P; Gomez, P; Alday, R

    2008-12-01

    In patients with traumatic spinal cord injury, several studies correlate neurological impairment and radiological findings. However, little information is available about this correspondence in the particular group of acute traumatic central cord syndrome. The object of the present work was to describe the clinical and radiological features of a series of patients presenting with acute traumatic central cord syndrome and to analyze clinical and radiological correlations on admission and at last follow-up. Retrospective review of 15 patients diagnosed of acute traumatic central cord syndrome between 1995 and 2005. Global motor score and motor score in upper extremities were determined on admission and at last follow-up (6 months-4 years, mean 16 months). Plain films, cervical computed tomography and magnetic resonance (MR) were performed in every patient and retrieved for the study. In seven patients, serial MR studies were performed during follow-up. Clinical and radiological correlations were statistically analyzed with non-parametric tests. Cervical spondylosis appeared associated with older age, falls, and absence of fracture. Spinal cord edema was the most common finding in MR studies but hemorrhage was also observed. The length of spinal cord edema significantly correlated with initial motor score. The decrease in T2-weighted hyperintensity in serial MR studies correlated with the gain of motor power in upper limbs at last follow-up. Elderly patients with more degenerated cervical spines commonly develop acute traumatic central cord syndrome after incidental falls. Length of spinal cord edema correlates with neurological impairment on admission and may provide significant prognostic information.

  20. RadCon: A Radiological Consequences Model

    International Nuclear Information System (INIS)

    Crawford, J.; Domel, R.U.

    2000-05-01

    RadCon estimates the dose received by user selected groups in the population from an accidental release of radionuclides to the environment. The exposure pathways considered are external exposure from the cloud and ground and internal exposure from inhalation and ingestion of contaminated food. Atmospheric dispersion modelling is carried out externally to RadCon.Given a two dimensional time varying air and ground concentration of radioactive elements, RadCon allows the user to: view the air and ground concentration over the affected area, select optional parameters and calculate the dose to people,display the results to the user, and change the parameter values. RadCon offers two user interfaces: 1) the standard graphical user interface which is started using Java DoseApp at the command line, or by setting up a shortcut to this command (particularly when RadCon is installed on a PC) and 2) the text based interface used to generate information for the model inter-comparison exercise . This is initiated using Java BIOMASS at the command line, or an equivalent shortcut. The text based interface was developed for research purposes and is not generally available. Appendices A, B and C provide a summary of instructions on setting up RadCon. This will generally be carried out by the computer support personnel

  1. Controlling the radiological impact in the nuclear fuel cycle: a cost/benefit analysis

    International Nuclear Information System (INIS)

    Blanco, R.E.

    1976-01-01

    Methods that are used to control the radiological impact of the nuclear fuel cycle are discussed. This control is exercised through the application of a series of Federal laws and regulations that are used as the basis for licensing nuclear facilities. These licenses contain technical specifications which define the limits for the release of radioactive materials. The control is exercised more directly in a technical sense by the use of radwaste treatment equipment at the nuclear facilities to limit the release of radioactive materials. The first part of this paper contains a summary of the principal Federal laws and regulations that apply to nuclear fuel cycle facilities and a description of how they are applied in licensing procedures. A detailed discussion is presented of the amounts of radioactive materials that may be released from licensed facilities, and the radiological doses that individuals and populations surrounding these facilities would receive from these releases. These doses are then compared with the radiological doses received from natural background radiation to put them in perspective. Cost/benefit engineering surveys which are being made to determine the cost (in dollars) and the effectiveness of radwaste systems for decreasing the release of radioactive materials from model fuel cycle facilities, and to determine the benefits in terms of reduction in dose commitment to individuals and populations in surrounding areas are described

  2. Prepopulated radiology report templates: a prospective analysis of error rate and turnaround time.

    Science.gov (United States)

    Hawkins, C M; Hall, S; Hardin, J; Salisbury, S; Towbin, A J

    2012-08-01

    Current speech recognition software allows exam-specific standard reports to be prepopulated into the dictation field based on the radiology information system procedure code. While it is thought that prepopulating reports can decrease the time required to dictate a study and the overall number of errors in the final report, this hypothesis has not been studied in a clinical setting. A prospective study was performed. During the first week, radiologists dictated all studies using prepopulated standard reports. During the second week, all studies were dictated after prepopulated reports had been disabled. Final radiology reports were evaluated for 11 different types of errors. Each error within a report was classified individually. The median time required to dictate an exam was compared between the 2 weeks. There were 12,387 reports dictated during the study, of which, 1,173 randomly distributed reports were analyzed for errors. There was no difference in the number of errors per report between the 2 weeks; however, radiologists overwhelmingly preferred using a standard report both weeks. Grammatical errors were by far the most common error type, followed by missense errors and errors of omission. There was no significant difference in the median dictation time when comparing studies performed each week. The use of prepopulated reports does not alone affect the error rate or dictation time of radiology reports. While it is a useful feature for radiologists, it must be coupled with other strategies in order to decrease errors.

  3. Cassini Spacecraft Uncertainty Analysis Data and Methodology Review and Update/Volume 1: Updated Parameter Uncertainty Models for the Consequence Analysis

    Energy Technology Data Exchange (ETDEWEB)

    WHEELER, TIMOTHY A.; WYSS, GREGORY D.; HARPER, FREDERICK T.

    2000-11-01

    Uncertainty distributions for specific parameters of the Cassini General Purpose Heat Source Radioisotope Thermoelectric Generator (GPHS-RTG) Final Safety Analysis Report consequence risk analysis were revised and updated. The revisions and updates were done for all consequence parameters for which relevant information exists from the joint project on Probabilistic Accident Consequence Uncertainty Analysis by the United States Nuclear Regulatory Commission and the Commission of European Communities.

  4. A comparison of the consequences of the design basis accident of the Greek Research Reactor with those of a serious realistic accident

    International Nuclear Information System (INIS)

    Kollas, J.G.; Anoussis, J.N.

    1985-12-01

    An analysis of the radiological consequences of the design basis and the coolant flow blockage accidents of the Greek Research Reactor is presented. The results indicate that the consequences of the coolant flow blockage accident are practically trivial being 1-2 orders of magnitude lower than the corresponding consequences of the design basis accident. (author)

  5. Preliminary radiological analysis of the transportation of contact-handled transuranic waste within the state of New Mexico. Revision 1

    International Nuclear Information System (INIS)

    Tappen, J.; Fredrickson, C.; Daer, G.

    1985-06-01

    This analysis assesses the potential radiological impacts on the citizens of New Mexico from the transport of CH-TRU waste to WIPP by rail or by truck. Assuming exclusive use of the truck transport mode, the combined annual exposure to the public from accident-free shipment of waste is estimated to be 3.3 person-rem/year. It is estimated that a theoretical member of the public receiving maximum exposure to the combined truck shipments of CH-TRU waste to WIPP would receive an annual whole body dose equivalent of 0.000016 rem. Such an exposure is insignificant in comparison to the average annual whole body dose equivalent to an individual living in the Colorado Plateau area of between 0.075 and 0.140 rem from natural occurring radiation. The combined annual radiological risk to the public living along the new Mexico truck routes to WIPP from potential accidents is projected as 0.031 person-rem/year. Assuming exclusive use of the rail transport mode, the combined annual exposure to the public from accident-free shipment of waste is estimated to be 1.2 person-rem/year. A theoretical member of the public receiving combined maximum exposure to rail shipments of CH-TRU waste to WIPP would receive an annual whole body dose equivalent of 0.000012 rem. The combined annual radiological risk to the public living along the New Mexico rail routes to WIPP from potential accidents is projected as 0.0022 person-rem/year. An estimate of the radiological impacts in a year of maximum waste receipt can be made by multiplying the above results for rail or truck by 2. This estimate is based upon the WIPP design waste throughput rate of 500,000 ft 3 per year. An estimate of the radiological impacts of CH-TRU waste transport to WIPP over the facility life can be made by multiplying the above results by 25

  6. Bibliometric analysis of the Spanish MR radiological production (2001-2007)

    International Nuclear Information System (INIS)

    Miguel-Dasit, Alberto; Marti-Bonmati, Luis; Sanfeliu, Pilar

    2008-01-01

    Objective: To evaluate the number and characteristics of papers on MR imaging written by radiologists in Spain and published in 2001-2007 Medline-indexed journals, including a comparison with the MR research output from German radiological departments. Materials and methods: Specific search profiles were devised to retrieve items from the Medline database. Relationship with the topic and major thematic areas of the articles, publication year, journal, language of publication, and mean impact factors were analyzed. Spanish and the German institutions with the highest MR productivity were identified. Also, the number of articles from Spain and Germany published in their respective official journals (Radiologia and ROFO) was recorded. Results: There were 332 Spanish articles published in 101 different journals. The higher number of papers was published in Spanish radiology and non-radiology journals (n = 105, 32%, mean IF: 0.191). The journal with the higher number of articles was Radiologia (n = 51, 15%). 'Neuroradiology' was the most frequent topic (n = 139, 42%). The Spanish productivity on MR imaging was yearly stable (p = 0.67), with the higher percentage of papers (17%) published in 2006. The topic with the higher IF was 'neuroradiology' (IF: 2.317). There were no yearly variations for the three major thematic areas ('Neuro imaging': p = 0.64; 'Body imaging': p = 0.91; and 'Non-clinical miscellanea': p = 0.46). The highest number of MR publications was found in two Spanish institutions (Dr. Peset University Hospital and Vall d'Hebron Hospital) (both, n = 28, 8%). In comparison, there were 1681 articles on MR imaging from Germany, having the two most productive institutions more than 150 papers in this period (University Hospital Essen and Eberhard-Karls University of Tuebingen). The adjusted number of articles per million populations was 20.4 for Germany and 8.1 for Spain. A total of 395 (23%) articles originating from Germany were published in the official

  7. Cost-consequence analysis of different active flowable hemostatic matrices in cardiac surgical procedures.

    Science.gov (United States)

    Makhija, D; Rock, M; Xiong, Y; Epstein, J D; Arnold, M R; Lattouf, O M; Calcaterra, D

    2017-06-01

    A recent retrospective comparative effectiveness study found that use of the FLOSEAL Hemostatic Matrix in cardiac surgery was associated with significantly lower risks of complications, blood transfusions, surgical revisions, and shorter length of surgery than use of SURGIFLO Hemostatic Matrix. These outcome improvements in cardiac surgery procedures may translate to economic savings for hospitals and payers. The objective of this study was to estimate the cost-consequence of two flowable hemostatic matrices (FLOSEAL or SURGIFLO) in cardiac surgeries for US hospitals. A cost-consequence model was constructed using clinical outcomes from a previously published retrospective comparative effectiveness study of FLOSEAL vs SURGIFLO in adult cardiac surgeries. The model accounted for the reported differences between these products in length of surgery, rates of major and minor complications, surgical revisions, and blood product transfusions. Costs were derived from Healthcare Cost and Utilization Project's National Inpatient Sample (NIS) 2012 database and converted to 2015 US dollars. Savings were modeled for a hospital performing 245 cardiac surgeries annually, as identified as the average for hospitals in the NIS dataset. One-way sensitivity analysis and probabilistic sensitivity analysis were performed to test model robustness. The results suggest that if FLOSEAL is utilized in a hospital that performs 245 mixed cardiac surgery procedures annually, 11 major complications, 31 minor complications, nine surgical revisions, 79 blood product transfusions, and 260.3 h of cumulative operating time could be avoided. These improved outcomes correspond to a net annualized saving of $1,532,896. Cost savings remained consistent between $1.3m and $1.8m and between $911k and $2.4m, even after accounting for the uncertainty around clinical and cost inputs, in a one-way and probabilistic sensitivity analysis, respectively. Outcome differences associated with FLOSEAL vs SURGIFLO

  8. Uncertainty and sensitivity analysis of chronic exposure results with the MACCS reactor accident consequence model

    International Nuclear Information System (INIS)

    Helton, J.C.; Johnson, J.D.; Rollstin, J.A.; Shiver, A.W.; Sprung, J.L.

    1995-01-01

    Uncertainty and sensitivity analysis techniques based on Latin hypercube sampling, partial correlation analysis and stepwise regression analysis are used in an investigation with the MACCS model of the chronic exposure pathways associated with a severe accident at a nuclear power station. The primary purpose of this study is to provide guidance on the variables to be considered in future review work to reduce the uncertainty in the important variables used in the calculation of reactor accident consequences. The effects of 75 imprecisely known input variables on the following reactor accident consequences are studied: crop growing season dose, crop long-term dose, water ingestion dose, milk growing season dose, long-term groundshine dose, long-term inhalation dose, total food pathways dose, total ingestion pathways dose, total long-term pathways dose, total latent cancer fatalities, area-dependent cost, crop disposal cost, milk disposal cost, population-dependent cost, total economic cost, condemnation area, condemnation population, crop disposal area and milk disposal area. When the predicted variables are considered collectively, the following input variables were found to be the dominant contributors to uncertainty: dry deposition velocity, transfer of cesium from animal feed to milk, transfer of cesium from animal feed to meat, ground concentration of Cs-134 at which the disposal of milk products will be initiated, transfer of Sr-90 from soil to legumes, maximum allowable ground concentration of Sr-90 for production of crops, fraction of cesium entering surface water that is consumed in drinking water, groundshine shielding factor, scale factor defining resuspension, dose reduction associated with decontamination, and ground concentration of 1-131 at which disposal of crops will be initiated due to accidents that occur during the growing season

  9. Uncertainty and sensitivity analysis of food pathway results with the MACCS Reactor Accident Consequence Model

    International Nuclear Information System (INIS)

    Helton, J.C.; Johnson, J.D.; Rollstin, J.A.; Shiver, A.W.; Sprung, J.L.

    1995-01-01

    Uncertainty and sensitivity analysis techniques based on Latin hypercube sampling, partial correlation analysis and stepwise regression analysis are used in an investigation with the MACCS model of the food pathways associated with a severe accident at a nuclear power station. The primary purpose of this study is to provide guidance on the variables to be considered in future review work to reduce the uncertainty in the important variables used in the calculation of reactor accident consequences. The effects of 87 imprecisely-known input variables on the following reactor accident consequences are studied: crop growing season dose, crop long-term dose, milk growing season dose, total food pathways dose, total ingestion pathways dose, total long-term pathways dose, area dependent cost, crop disposal cost, milk disposal cost, condemnation area, crop disposal area and milk disposal area. When the predicted variables are considered collectively, the following input variables were found to be the dominant contributors to uncertainty: fraction of cesium deposition on grain fields that is retained on plant surfaces and transferred directly to grain, maximum allowable ground concentrations of Cs-137 and Sr-90 for production of crops, ground concentrations of Cs-134, Cs-137 and I-131 at which the disposal of milk will be initiated due to accidents that occur during the growing season, ground concentrations of Cs-134, I-131 and Sr-90 at which the disposal of crops will be initiated due to accidents that occur during the growing season, rate of depletion of Cs-137 and Sr-90 from the root zone, transfer of Sr-90 from soil to legumes, transfer of Cs-137 from soil to pasture, transfer of cesium from animal feed to meat, and the transfer of cesium, iodine and strontium from animal feed to milk

  10. Uncertainty and sensitivity analysis of food pathway results with the MACCS reactor accident consequence model

    International Nuclear Information System (INIS)

    Helton, J.C.; Johnson, J.D.; Rollstin, J.A.; Shiver, A.W.; Sprung, J.L.

    1995-01-01

    Uncertainty and sensitivity analysis techniques based on Latin hypercube sampling, partial correlation analysis and stepwise regression analysis are used in an investigation with the MACCS model of the food pathways associated with a severe accident at a nuclear power station. The primary purpose of this study is to provide guidance on the variables to be considered in future review work to reduce the uncertainty in the important variables used in the calculation of reactor accident consequences. The effects of 87 imprecisely-known input variables on the following reactor accident consequences are studied: crop growing-season dose, crop long-term dose, milk growing-season dose, total food pathways dose, total ingestion pathways dose, total long-term pathways dose, area dependent cost, crop disposal cost, milk disposal cost, condemnation area, crop disposal area and milk disposal area. When the predicted variables are considered collectively, the following input variables were found to be the dominant contributors to uncertainty: fraction of cesium deposition on grain fields that is retained on plant surfaces and transferred directly to grain, maximum allowable ground concentrations of Cs-137 and Sr-90 for production of crops, ground concentrations of Cs-134, Cs-137 and I-131 at which the disposal of milk will be initiated due to accidents that occur during the growing season, ground concentrations of Cs-134, I-131 and Sr-90 at which the disposal of crops will be initiated due to accidents that occur during the growing season, rate of depletion of Cs-137 and Sr-90 from the root zone, transfer of Sr-90 from soil to legumes, transfer of Cs-137 from soil to pasture, transfer of cesium from animal feed to meat, and the transfer of cesium, iodine and strontium from animal feed to milk

  11. Uncertainty and sensitivity analysis of chronic exposure results with the MACCS reactor accident consequence model

    International Nuclear Information System (INIS)

    Helton, J.C; Johnson, J.D; Rollstin, J.A; Shiver, A.W; Sprung, J.L

    1995-01-01

    Uncertainty and sensitivity analysis techniques based on Latin hypercube sampling, partial correlation analysis and stepwise regression analysis are used in an investigation with the MACCS model of the chronic exposure pathways associated with a severe accident at a nuclear power station. The primary purpose of this study is to provide guidance on the variables to be considered in future review work to reduce the uncertainty in the important variables used in the calculation of reactor accident consequences. The effects of 75 imprecisely known input variables on the following reactor accident consequences are studied: crop growing-season dose, crop long-term dose, water ingestion dose, milk growing-season dose, long-term groundshine dose, long-term inhalation dose, total food pathways dose, total ingestion pathways dose, total long-term pathways dose, total latent cancer fatalities, area-dependent cost, crop disposal cost, milk disposal cost, population-dependent cost, total economic cost, condemnation area, condemnation population, crop disposal area and milk disposal area. When the predicted variables are considered collectively, the following input variables were found to be the dominant contributors to uncertainty: dry deposition velocity, transfer of cesium from animal feed to milk, transfer of cesium from animal feed to meet, ground concentration of Cs-134 at which the disposal of milk products will be initiated, transfer of Sr-90 from soil to legumes, maximum allowable ground concentration of Sr-90 for production of crops, fraction of cesium entering surface water that is consumed in drinking water, groundshine shielding factor, scale factor defining resuspension, dose reduction associated with decontamination, and ground concentration of I-131 at which disposal of crops will be initiated due to accidents that occur during the growing season. Reducing the uncertainty in the preceding variables was found t