WorldWideScience

Sample records for assess radiological risk

  1. Radiological safety and risk assessment

    International Nuclear Information System (INIS)

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

    1982-02-01

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

  2. Radiological risk assessment of a radioactively contaminated site

    International Nuclear Information System (INIS)

    Devgun, J.S.

    1990-01-01

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

  3. Radiological risk assessment of environmental radon

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-11-27

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-03-01

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

  5. Radiological endpoints relevant to ecological risk assessment

    International Nuclear Information System (INIS)

    Harrison, F.

    1997-01-01

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

  6. Radiological risk assessment for radioactive contamination at landfill site

    International Nuclear Information System (INIS)

    Devgun, J.S.

    1990-01-01

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

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

    International Nuclear Information System (INIS)

    Lee, Alex; Mathers, Dan

    2003-01-01

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

  8. Depleted uranium residual radiological risk assessment for Kosovo sites

    International Nuclear Information System (INIS)

    Durante, Marco; Pugliese, Mariagabriella

    2003-01-01

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

  9. Assessment of the radiation risk from diagnostic radiology

    International Nuclear Information System (INIS)

    Streffer, C.; Mueller, W.U.

    1995-01-01

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

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

    International Nuclear Information System (INIS)

    Chinyama, Catherine N.

    2014-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-04-01

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

  12. Principles and issues in radiological ecological risk assessment.

    Science.gov (United States)

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

    2003-01-01

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

  13. Radiological Risk Assessment of Capstone Depleted Uranium Aerosols

    International Nuclear Information System (INIS)

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

    2009-01-01

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

  14. Radiological risk assessment of Capstone depleted uranium aerosols.

    Science.gov (United States)

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

    2009-03-01

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

  15. A comparison of radiological risk assessment methods for environmental restoration

    International Nuclear Information System (INIS)

    Dunning, D.E. Jr.; Peterson, J.M.

    1993-01-01

    Evaluation of risks to human health from exposure to ionizing radiation at radioactively contaminated sites is an integral part of the decision-making process for determining the need for remediation and selecting remedial actions that may be required. At sites regulated under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), a target risk range of 10 -4 to 10 -6 incremental cancer incidence over a lifetime is specified by the US Environmental Protection Agency (EPA) as generally acceptable, based on the reasonable maximum exposure to any individual under current and future land use scenarios. Two primary methods currently being used in conducting radiological risk assessments at CERCLA sites are compared in this analysis. Under the first method, the radiation dose equivalent (i.e., Sv or rem) to the receptors of interest over the appropriate period of exposure is estimated and multiplied by a risk factor (cancer risk/Sv). Alternatively, incremental cancer risk can be estimated by combining the EPA's cancer slope factors (previously termed potency factors) for radionuclides with estimates of radionuclide intake by ingestion and inhalation, as well as radionuclide concentrations in soil that contribute to external dose. The comparison of the two methods has demonstrated that resulting estimates of lifetime incremental cancer risk under these different methods may differ significantly, even when all other exposure assumptions are held constant, with the magnitude of the discrepancy depending upon the dominant radionuclides and exposure pathways for the site. The basis for these discrepancies, the advantages and disadvantages of each method, and the significance of the discrepant results for environmental restoration decisions are presented

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

    International Nuclear Information System (INIS)

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

    2007-11-01

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

  17. Assessment of risk in radiology using malpractice RVU

    International Nuclear Information System (INIS)

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

    2007-01-01

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

  18. Assessment of risk in radiology using malpractice RVU

    Energy Technology Data Exchange (ETDEWEB)

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

    2007-02-15

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

  19. Radiological protection criteria risk assessments for waste disposal options

    International Nuclear Information System (INIS)

    Hill, M.D.

    1982-01-01

    Radiological protection criteria for waste disposal options are currently being developed at the National Radiological Protection Board (NRPB), and, in parallel, methodologies to be used in assessing the radiological impact of these options are being evolved. The criteria and methodologies under development are intended to apply to all solid radioactive wastes, including the high-level waste arising from reprocessing of spent nuclear fuel (because this waste will be solidified prior to disposal) and gaseous or liquid wastes which have been converted to solid form. It is envisaged that the same criteria will be applied to all solid waste disposal options, including shallow land burial, emplacement on the ocean bed (sea dumping), geological disposal on land and sub-seabed disposal

  20. Assessing radiologic risk for population due to human activities

    International Nuclear Information System (INIS)

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

    2002-01-01

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

  1. Principles and issues in radiological ecological risk assessment

    International Nuclear Information System (INIS)

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

    2003-01-01

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

  2. Assessment of radiological risks at the ATLAS experiment

    International Nuclear Information System (INIS)

    Zajacova, Z.

    2009-07-01

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

  3. Radiological Risk Assessment for King County Wastewater Treatment Division

    Energy Technology Data Exchange (ETDEWEB)

    Strom, Daniel J.

    2005-08-05

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

  4. New concepts in risk assessment for patients with radiological treatment

    International Nuclear Information System (INIS)

    Tautz, M.; Brandt, G.A.

    1986-01-01

    In radiation risk assessment it must be differentiated between somatic and genetic effect on the one hand as well as between stochastic and non-stochastic effect on the other. According to definitions of the ICRP report 26 the limit for the dose equivalent of all tissues prevents non-stochastic radiation effects. With stochastic radiation effects probably exist no threshold doses; therefore the ALARA principle must be applied concerning radiation protection. The individual risk by stochastic radiation effects in its linear, linear-quadratic and quadratic extrapolations, respectively, is discussed in detail. The effective stochastic dose equivalent (H/sub eff/) as well as collective dose and collective damage are outlined

  5. Radiological risk assessment of use of phosphate fertilizers in soil

    International Nuclear Information System (INIS)

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

    2006-01-01

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

  6. 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)

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

    International Nuclear Information System (INIS)

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

    2007-01-01

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

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

    International Nuclear Information System (INIS)

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

    2009-01-01

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

  9. An overall genetic risk assessment for radiological protection purposes

    International Nuclear Information System (INIS)

    Oftedal, P.; Searle, A.G.

    1980-01-01

    Risks of serious hereditary damage in the first and second generations after low level radiation exposure and at equilibrium were calculated by using a doubling dose of 100 rem (based on experimental work with the mouse) and by considering separately the various categories of genic and chromosomal defect. Prenatal lethality was not included. It is estimated that after the exposure of a population of future parents to a collective dose of 1 million man-rem, about 125 extra cases of serious genetic ill health would appear in children and grandchildren. In all future generations, a total of about 320 cases is expected, provided the population remains of constant size. It is emphasised however, that a number of major assumptions have to be made in order to arrive at any overall genetic risk estimate, so that the confidence limits of these figures are bound to be wide. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-07-01

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

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

    Science.gov (United States)

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

    2013-11-01

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

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

    Science.gov (United States)

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

    2018-04-01

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

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

    International Nuclear Information System (INIS)

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

    1985-08-01

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

  14. Radiological risk comparison guidelines

    International Nuclear Information System (INIS)

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

    1992-01-01

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

  15. Assessment of radiological risk in vicinity of former uranium mining areas in Poland

    Energy Technology Data Exchange (ETDEWEB)

    Ciupek, K.; Krajewski, P.; Kardas, M.; Suplinska, M. [Central Laboratory for Radiological Protection (Poland)

    2014-07-01

    The work carried out under the project NCBiR - 'Technologies Supporting Development of Safe Nuclear Power Engineering'; Task 3: Meeting the Polish nuclear power engineering's demand for fuel - fundamental aspects. Human activities related to the use of ionizing radiation and radioactive substances might cause exposure of the population and the environment. However, radiological risk assessment is mainly conducted only to human as an estimation of the effective dose being the sum of external and internal exposure whereas environmental protection assessment is more complex studies. The increased interest in recent years in this aspect and the ability to perform computer simulations contributed the development of models enabling assessment of exposure to certain organisms and estimation the concentrations of radionuclides in the various components of the environment. These models define a possible transition path of radionuclide in the atmosphere or waterways through their physical parameterization. The estimation of the content of radionuclides in plants, animals and human is possible by applying an existing risk assessment methodology. Models assessing human and environmental exposure from natural and artificial radionuclides, such as CROM, RESRAD, IMPACT or ERICA, come to be useful tools not only for researchers but also for regulatory authorities. This case study focused on the uranium mining areas (inactive mines and waste dumps) in the Giant Mountains (Karkonosze Mountains) in the south-west of Poland. On the basis of activity concentrations in samples of soil and mineral material from mine shafts, water samples from ponds, streams and small rivers and vegetation samples, an assessment of radiological impact of the former uranium mining areas was performed. The doses for reference group of inhabitants and biota in the vicinity of the former uranium mine were evaluated using IMPACT (EcoMetrix Inc.) model and ERICA tool. The variability and

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

    International Nuclear Information System (INIS)

    Johnson, K.; Lucas, R.

    1986-12-01

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

  17. A Probabilistic Assessment of the Chemical and Radiological Risks of Chronic Exposure to Uranium in Freshwater Ecosystems

    International Nuclear Information System (INIS)

    Mathews, T.; Beaugelin-Seiller, K.; Garnier-Laplace, J.; Gilbin, R.; Adam, Ch.; Della-Vedova, C.

    2009-01-01

    Uranium (U) presents a unique challenge for ecological risk assessments (ERA) because it induces both chemical and radiological toxicity, and the relative importance of these two toxicities differs among the various U source terms (i.e., natural, enriched, depleted). We present a method for the conversion between chemical concentrations (μgL -1 ) and radiological dose rates (μGyh -1 ) for a defined set of reference organisms, and apply this conversion method to previously derived chemical and radiological benchmarks to determine the extent to which these benchmarks ensure radiological and chemical protection, respectively, for U in freshwater ecosystems. Results show that the percentage of species radiologically protected by the chemical benchmark decreases with increasing degrees of U enrichment and with increasing periods of radioactive decay. In contrast, the freshwater ecosystem is almost never chemically protected by the radiological benchmark, regardless of the source term or decay period considered, confirming that the risks to the environment from uranium's chemical toxicity generally outweigh those of its radiological toxicity. These results are relevant to developing water quality criteria that protect freshwater ecosystems from the various risks associated with the nuclear applications of U exploitation, and highlight the need for (1) further research on the speciation, bioavailability, and toxicity of U-series radionuclides under different environmental conditions, and (2) the adoption of both chemical and radiological benchmarks for coherent ERAS to be conducted in U-contaminated freshwater ecosystems. (authors)

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

    International Nuclear Information System (INIS)

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

    1998-01-01

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

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

    International Nuclear Information System (INIS)

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

    2004-01-01

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

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

    Science.gov (United States)

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

    2018-02-01

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

  1. 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

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

    International Nuclear Information System (INIS)

    Wahl, L.E.

    1994-03-01

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

  3. Risks from dental radiology

    International Nuclear Information System (INIS)

    Costa, Tamara Goularte

    2013-01-01

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

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

    International Nuclear Information System (INIS)

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

    2001-01-01

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

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

    International Nuclear Information System (INIS)

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

    2005-01-01

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

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

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  7. Risk versus benefit in radiology

    International Nuclear Information System (INIS)

    Samuel, E.

    1985-01-01

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

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

    International Nuclear Information System (INIS)

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

    2009-01-01

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

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

    International Nuclear Information System (INIS)

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

    2017-01-01

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

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

    International Nuclear Information System (INIS)

    Larsson, C.L.

    2004-12-01

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

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

    International Nuclear Information System (INIS)

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

    2001-01-01

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

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

    Science.gov (United States)

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

    2016-07-01

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

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

    International Nuclear Information System (INIS)

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

    1994-01-01

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

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

    International Nuclear Information System (INIS)

    Zajacova, Z.

    2009-01-01

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

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

    International Nuclear Information System (INIS)

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

    2010-01-01

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

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

    International Nuclear Information System (INIS)

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

    1996-06-01

    This report presents the results of task B.3 of the 'Technology Assessment of the High Temperature Reactor' project. The objective of task B.3 was to evaluate the radiological risks to the general public associated with the sustainable HTGR cycle. Since the technologies to be used at several stages of this fuel cycle are still in the design phase and since a detailed specification of this fuel cycle has not yet been developed, the emphasis was on obtaining a global impression of the risk associated with a generic thorium-based HTGR fuel cycle. This impression was obtained by performing a comparative risk analysis on the basis of data given in the literature. As reference for the comparison a generic uranium fuel led LWR cycle was used. The structure of the report is as follows. In Chapter 2 the general methodology for assessing the radiological risks associated with nuclear installations is described. An overview is given of the measures commonly used to quantify these risks. In Chapter 3 an overview is given of the different stages of the reference uranium fuel led LWR cycle and the thorium fuel led HTGR cycle. In Chapter 4 a stage-by-stage analysis is given of the radiological risks associated with the two fuel cycles. Finally, in Chapter 5 an evaluation is made of the radiological risks associated with the LWR and HTGR cycles and with thorium and uranium fuels. In Appendix A the production and releases of 14 C for LWR and HTGR fuel cycle facilities is considered in detail. 11 figs., 10 tabs., 10 refs

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

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  18. Radiological risk perception in Spain

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  19. Environmental Tools and Radiological Assessment

    Science.gov (United States)

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

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

    International Nuclear Information System (INIS)

    Mancioppi, S.; Piermattei, S.

    1985-01-01

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

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

    International Nuclear Information System (INIS)

    Thorne, M.C.

    1988-12-01

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

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

    International Nuclear Information System (INIS)

    Vieru, G.

    2000-01-01

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

  3. Introduction to radiological performance assessment

    International Nuclear Information System (INIS)

    Moss, G.

    1995-02-01

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

  4. Assessment and management of cancer risks from radiological and chemical hazards

    International Nuclear Information System (INIS)

    1998-01-01

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

  5. RESRAD for Radiological Risk Assessment. Comparison with EPA CERCLA Tools - PRG and DCC Calculators

    Energy Technology Data Exchange (ETDEWEB)

    Yu, C. [Argonne National Lab. (ANL), Argonne, IL (United States); Cheng, J. -J. [Argonne National Lab. (ANL), Argonne, IL (United States); Kamboj, S. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2015-07-01

    The purpose of this report is two-fold. First, the risk assessment methodology for both RESRAD and the EPA’s tools is reviewed. This includes a review of the EPA’s justification for 2 using a dose-to-risk conversion factor to reduce the dose-based protective ARAR from 15 to 12 mrem/yr. Second, the models and parameters used in RESRAD and the EPA PRG and DCC Calculators are compared in detail, and the results are summarized and discussed. Although there are suites of software tools in the RESRAD family of codes and the EPA Calculators, the scope of this report is limited to the RESRAD (onsite) code for soil contamination and the EPA’s PRG and DCC Calculators also for soil contamination.

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

    International Nuclear Information System (INIS)

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

    2006-01-01

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

  7. Health Risks of Diagnostic Radiology

    International Nuclear Information System (INIS)

    Al-Oraby, M.N.A.

    2014-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Green, J.R.

    1995-01-31

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

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

    International Nuclear Information System (INIS)

    Green, J.R.

    1995-01-01

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

  10. Radiological assessement of Crohn's disease

    International Nuclear Information System (INIS)

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

    1987-01-01

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

  11. Radiation Protection Research: Radiological Assessment

    International Nuclear Information System (INIS)

    Zeevaert, T.

    2000-01-01

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

  12. The development and application of an integrated radiological risk assessment procedure using time-dependent probabilistic risk analysis

    International Nuclear Information System (INIS)

    Laurens, J.M.; Thompson, B.G.J.; Sumerling, T.J.

    1990-01-01

    During the past decade, the UKDoE has funded the development of an integrated assessment procedure centred around probabilistic risk analysis (p.r.a.) using Monte Carlo simulation techniques to account for the effects of parameter value uncertainty, including those associated with temporal changes in the environment over a postclosure period of about one million years. The influence of these changes can now be incorporated explicitly into the p.r.a. simulator VANDAL (Variability ANalysis of Disposal ALternatives) briefly described here. Although a full statistically converged time-dependent p.r.a. will not be demonstrated until the current Dry Run 3 trial is complete, illustrative examples are given showing the ability of VANDAL to represent spatially complex groundwater and repository systems evolving under the influence of climatic change. 18 refs., 10 figs., 1 tab

  13. Assessment of the radiological risks of road transport accidents involving type A-packages

    International Nuclear Information System (INIS)

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

    1998-10-01

    This document, prepared in the framework of a study for the European Commission, presents the evaluation of the risks of accidents associated to the road transport of type A-packages (primarily packages of radio-pharmaceutic or radiography products) for five countries of the European Union. The annual transport of type A-packages varies considerably from one country to another, some countries being producers of radio-pharmaceutic products, others not. These packages are also very different one from each another: the weight varies generally from 1 to 25 kg and the activity from some Mega-Becquerels to few tens of Giga-Becquerels, the average activity expressed in A 2 is 0,01. (A.L.B.)

  14. Dose assessment in radiological accidents

    International Nuclear Information System (INIS)

    Donkor, S.

    2013-04-01

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

  15. Assessment of atmospherically-released radionuclides using the computerized radiological risk investigation system

    International Nuclear Information System (INIS)

    Nelson, C.B.; Sjoreen, A.L.; Miller, C.W.; Baes, C.F. III.

    1986-01-01

    For radionuclides, the standards are in terms of an annual dose, and the regulations require assurance that no member of the general public receives a dose in excess of that standard. Thus, spatial variations in the population around an emission source must be considered. Furthermore, for most chemical pollutants the standards are written in terms of an air concentration while for radionuclides other pathways of exposure, e.g., uptake of the airborne emissions by terrestrial food chains must also be considered. The remainder of this paper discusses the computer codes that make up the CRRIS and how they are used to perform an assessment of the health impacts on man of radionuclides released to the atmosphere

  16. Radiological risk assessment and biosphere modelling for radioactive waste disposal in Switzerland.

    Science.gov (United States)

    Brennwald, M S; van Dorp, F

    2009-12-01

    Long-term safety assessments for geological disposal of radioactive waste in Switzerland involve the demonstration that the annual radiation dose to humans due to the potential release of radionuclides from the waste repository into the biosphere will not exceed the regulatory limit of 0.1 mSv. Here, we describe the simple but robust approach used by Nagra (Swiss National Cooperative for the Disposal of Radioactive Waste) to quantify the dose to humans as a result to time-dependent release of radionuclides from the geosphere into the biosphere. The model calculates the concentrations of radionuclides in different terrestrial and aquatic compartments of the surface environment. The fluxes of water and solids within the environment are the drivers for the exchange of radionuclides between these compartments. The calculated radionuclide concentrations in the biosphere are then used to estimate the radiation doses to humans due to various exposure paths (e.g. ingestion of radionuclides via drinking water and food, inhalation of radionuclides, external irradiation from radionuclides in soils). In this paper we also discuss recent new achievements and planned future work.

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

    International Nuclear Information System (INIS)

    Myers, D.K.

    1997-01-01

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

  18. Predictions of models for environmental radiological assessment

    International Nuclear Information System (INIS)

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

    2011-01-01

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

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

    Science.gov (United States)

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

    2015-01-01

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

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

    International Nuclear Information System (INIS)

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

    1986-02-01

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

  1. Assessment of Chemical and Radiological Vulnerabilities

    International Nuclear Information System (INIS)

    SETH, S.S.

    2000-01-01

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

  2. Development of a methodology for post closure radiological risk analysis of underground waste repositories. Illustrative assessment of the Harwell site

    International Nuclear Information System (INIS)

    Gralewski, Z.A.; Kane, P.; Nicholls, D.B.

    1987-06-01

    A probabilistic risk analysis (pra) is demonstrated for a number of ground water mediated release scenarios at the Harwell Site for a hypothetical repository at a depth of about 150 metres. This is the second stage of development of an overall risk assessment methodology. A procedure for carrying out multi-scenario assessment using available probabilistic risk assessment (pra) models is presented and a general methodology for combining risk contributions is outlined. Appropriate levels of model complexity in pra are discussed. Modelling requirements for the treatment of multiple simultaneous pathways and of site evolution are outlined. Further developments of pra systems are required to increase the realism of both the models and their mode of application, and hence to improve estimates of risk. (author)

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

    Science.gov (United States)

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

    2017-03-01

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

  4. Radiological assessments for the National Ignition Facility

    International Nuclear Information System (INIS)

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

    1996-01-01

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

  5. Radiologic sciences. Faculty needs assessment.

    Science.gov (United States)

    Powers, Kevin J

    2005-01-01

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

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

    International Nuclear Information System (INIS)

    Oliveira Loureiro, C. de; Yu, C.

    1995-01-01

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

  7. Estimation of Radiological Terrorism Risk by Administrative Districts

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-10-15

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

  8. Estimation of Radiological Terrorism Risk by Administrative Districts

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  9. A probabilistic approach to Radiological Environmental Impact Assessment

    International Nuclear Information System (INIS)

    Avila, Rodolfo; Larsson, Carl-Magnus

    2001-01-01

    Since a radiological environmental impact assessment typically relies on limited data and poorly based extrapolation methods, point estimations, as implied by a deterministic approach, do not suffice. To be of practical use for risk management, it is necessary to quantify the uncertainty margins of the estimates as well. In this paper we discuss how to work out a probabilistic approach for dealing with uncertainties in assessments of the radiological risks to non-human biota of a radioactive contamination. Possible strategies for deriving the relevant probability distribution functions from available empirical data and theoretical knowledge are outlined

  10. BURYIT/ANALYZ: a computer package for assessment of radiological risk of low-level radioactive waste land disposal

    International Nuclear Information System (INIS)

    Fisher, J.E.; Cox, N.D.; Atwood, C.L.

    1984-11-01

    This report is a user's manual for a partially completed code for risk assessment of a low-level waste shallow-land burial site, to be used in the licensing of burial sites. This code is intended as a tool to be used for considering nuclide transport mechanisms, including atmospheric, groundwater, erosion, and infiltration to an underlying aquifer. It also calculates doses to individuals and the population through direct exposure, inhalation, and ingestion. The methodology of the risk assessment is based primarily on the response surface method of uncertainty analysis. The parameters of a model for predicting dose commitment due to a release are treated as statistical variables in order to compute statistical distributions for various dose commitment contributions. The likelihood of a release is also accounted for by statistically evaluating the arithmetic product of the dose commitment distributions with the probability of release occurrence. An example is given using the atmospheric transport pathway as modeled by a code called BURYIT. The framework for using other release pathways is described in this manual. Information on parameter uncertainties, reference site characteristics, and probabilities of release events is included

  11. Development of mobile radiological assessment laboratory

    International Nuclear Information System (INIS)

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

    2018-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-05-01

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

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

    International Nuclear Information System (INIS)

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

    1996-05-01

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

  14. Risk Assessment

    Science.gov (United States)

    How the EPA conducts risk assessment to protect human health and the environment. Several assessments are included with the guidelines, models, databases, state-based RSL Tables, local contacts and framework documents used to perform these assessments.

  15. Radiological risks and civil liability

    International Nuclear Information System (INIS)

    Miller, C.E.

    1989-01-01

    In this paper, attention is first concentrated on the substantive issue of nuclear safety-a matter on which, Friends of the Earth claimed, the Secretary of State had misdirected himself in law. The Court of Appeal's interpretation of a central element of the Nuclear Installations Act 1965 implies certain inherent problems associated with the law relating to compensation for radiation-induced injury. These problems-on the nature of causation and strict liability-are such that they cannot be solved by simple reform of current law and, it is further argued, extra-legal means of compensating those affected by radiation (and other environmental agents) are required. Before attempting to justify this assertion, it is necessary to examine the substance of the judgement in more detail. First the nature of acceptable risk is considered from absolutist and probabalistic viewpoints. The permitted discharges are reviewed followed by a discussion of the accidental discharges of radioactivity into the environment. Incidents at BNFL's Sellafield site are listed. Genetic risks are also considered. The notion of strict liability is discussed for radiation-induced injury, and an alternative approach of increased social security payments financed in part by those organisations discharging radioactivity into the environment is considered. (author)

  16. Radiological risks and civil liability

    Energy Technology Data Exchange (ETDEWEB)

    Miller, C.E. (Salford Univ. (UK). Environmental Health and Housing Div.)

    1989-01-01

    In this paper, attention is first concentrated on the substantive issue of nuclear safety-a matter on which, Friends of the Earth claimed, the Secretary of State had misdirected himself in law. The Court of Appeal's interpretation of a central element of the Nuclear Installations Act 1965 implies certain inherent problems associated with the law relating to compensation for radiation-induced injury. These problems-on the nature of causation and strict liability-are such that they cannot be solved by simple reform of current law and, it is further argued, extra-legal means of compensating those affected by radiation (and other environmental agents) are required. Before attempting to justify this assertion, it is necessary to examine the substance of the judgement in more detail. First the nature of acceptable risk is considered from absolutist and probabalistic viewpoints. The permitted discharges are reviewed followed by a discussion of the accidental discharges of radioactivity into the environment. Incidents at BNFL's Sellafield site are listed. Genetic risks are also considered. The notion of strict liability is discussed for radiation-induced injury, and an alternative approach of increased social security payments financed in part by those organisations discharging radioactivity into the environment is considered. (author).

  17. Radiological risk in case of potential exposures

    International Nuclear Information System (INIS)

    Chiossi, C.E.

    1998-01-01

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

  18. CRRIS: a computerized radiological risk-investigation system

    International Nuclear Information System (INIS)

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

    1981-01-01

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

  19. Risk assessment

    International Nuclear Information System (INIS)

    Kinchin, G.H.

    1983-01-01

    After defining risk and introducing the concept of individual and societal risk, the author considers each of these, restricting considerations to risk of death. Some probabilities of death arising from various causes are quoted, and attention drawn to the care necessary in making comparisons between sets of data and to the distinction between voluntary and involuntary categories and between early and delayed deaths. The presentation of information on societal risk is discussed and examples given. The history of quantified risk assessment is outlined, particularly related to the nuclear industry, the process of assessing risk discussed: identification of hazard causes, the development of accident chains and the use of event trees, the evaluation of probability through the collection of data and their use with fault trees, and the assessment of consequences of hazards in terms of fatalities. Reference is made to the human element and common-made failures, and to studies supporting the development of reliability assessment techniques. Acceptance criteria are discussed for individual and societal risk in the nuclear field, and it is shown that proposed criteria lead to risks conservative by comparison with risks from day-to-day accidents and other potentially hazardous industries. (U.K.)

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

    International Nuclear Information System (INIS)

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

    2002-01-01

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

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

    International Nuclear Information System (INIS)

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

    2011-01-01

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

  2. Relative radiological risks derived from different TENORM wastes in Malaysia.

    Science.gov (United States)

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

    2011-11-01

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

  3. Relative radiological risks derived from different TENORM wastes in Malaysia

    International Nuclear Information System (INIS)

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

    2011-01-01

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

  4. [Optimization of radiological scoliosis assessment].

    Science.gov (United States)

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

    2014-07-01

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

  5. Radiology and risk: an economist's perspective

    International Nuclear Information System (INIS)

    Mooney, G.H.

    1981-01-01

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

  6. Risk Assessment

    OpenAIRE

    Hrdová, Edita

    2012-01-01

    This diploma thesis is focused on companies risk evaluation before endorsement of Loan deriving from business relationships. The aim of this thesis is not only to describe individual steps of risk assessment, but also perfom analysis of particular companies based on available data, i.e. Balance sheet, Profit and Loss statement and external rating and after that propose solution for each company. My analysis will be based on theoretical knowledge, further on experience related to my job role a...

  7. Risk assessment

    DEFF Research Database (Denmark)

    Pedersen, Liselotte; Rasmussen, Kirsten; Elsass, Peter

    2010-01-01

    International research suggests that using formalized risk assessment methods may improve the predictive validity of professionals' predictions of risk of future violence. This study presents data on forensic psychiatric patients discharged from a forensic unit in Denmark in year 2001-2002 (n=107...... and the individual dynamic items strengthen the use of this scheme in clinical practice. (PsycINFO Database Record (c) 2010 APA, all rights reserved) (journal abstract)...

  8. The development by means of trial assessments, of a procedure for radiological risk assessment of underground disposal of low and intermediate level radioactive wastes

    International Nuclear Information System (INIS)

    Thompson, B.G.J.

    1987-01-01

    Seven trials are outlined showing the development and testing of a procedure based upon pra using Monte Carlo simulators, to assess post closure risks from the underground disposal of low and intermediate level radioactive wastes. The PRA method is found to be more justifiable than the use of 'best estimates'. Problems of accounting for long-term environmental changes and of future human intrusions are discussed. The importance of achieving statistical convergence within practical time scales and resources and of accounting for the influence of different sources of systematic bias is emphasised. (orig.)

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

    Science.gov (United States)

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

    2018-05-01

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

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

    International Nuclear Information System (INIS)

    1998-01-01

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

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

    International Nuclear Information System (INIS)

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

    1986-09-01

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

  12. Radiological assessments, environmental monitoring, and study design

    International Nuclear Information System (INIS)

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

    1980-01-01

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

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

    DEFF Research Database (Denmark)

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

    1998-01-01

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

  14. Probabilistic Radiological Performance Assessment Modeling and Uncertainty

    Science.gov (United States)

    Tauxe, J.

    2004-12-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2005-07-01

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

  16. Radiological assessment of the PET facility

    International Nuclear Information System (INIS)

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

    2008-01-01

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

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

    International Nuclear Information System (INIS)

    Gauron, C.

    2009-01-01

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

  18. Models and parameters for environmental radiological assessments

    International Nuclear Information System (INIS)

    Miller, C.W.

    1983-01-01

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

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

    International Nuclear Information System (INIS)

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

    1995-10-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-10-01

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

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

    Science.gov (United States)

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

    2013-11-01

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

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

    International Nuclear Information System (INIS)

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

    2013-01-01

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

  3. Development of a methodology for post closure radiological risk analysis of underground waste repositories. Illustrative assessment of the Harwell site. V.1

    International Nuclear Information System (INIS)

    Gralewski, Z.A.; Kane, P.; Nicholls, D.B.

    1987-06-01

    A probabilistic risk analysis (pra) is demonstrated for a number of ground water mediated release scenarios at the Harwell Site for a hypothetical repository at a depth of about 150 metres. This is the second stage of development of an overall risk assessment methodology. A procedure for carrying out multi-scenario assessment using available probabilistic risk assessment (pra) models is presented and a general methodology for combining risk contributions is outlined. Appropriate levels of model complexity in pra are discussed. Modelling requirements for the treatment of multiple simultaneous pathways and of site evolution are outlined. Further developments of pra systems are required to increase the realism of both the models and their mode of application, and hence to improve estimates of risk. (author)

  4. Assessment of radiological risk parameters associated with some selected rivers around oil mineral producing sites in Abia State, Nigeria due to gross alpha and beta radiations

    International Nuclear Information System (INIS)

    Enyinna, Paschal Ikenna; Uzochukwu, Francis C.

    2016-01-01

    The study of gross alpha and beta radiation in environmental components and water bodies in particular is very crucial to the environmental, radiation and medical Physicist as this helps to promote good water quality and environmental hygiene. This research work understudied the radiological risk parameters due to gross alpha and beta radiations associated with three selected rivers around crude oil production sites in Abia State, Nigeria. Gross alpha and beta activities were computed for the three rivers based on analytical measurements carried out using a well-calibrated IN-20 model gas-flow proportional counter. Radiological risk parameters were computed from the activity concentrations which included; annual effective dose equivalent of radiation from ingested water (AEDE), annual gonadal dose equivalent (AGDE), and excess lifetime cancer risk (ELCR). The mean of the total AEDE due to the sum of alpha and beta radiations for the three rivers are 0.868 ± 0.221 mSv/y, 1.008 ± 0.156 mSv/y, and 0.917 ± 0.214 mSv/y; and are above the World Health Organization (WHO) permissible limit of 0.1 mSv/y. The mean of the total AGDE are 4.048 ± 1.063 mSv/y, 4.756 ± 0.739 mSv/y, and 4.295 ± 1.026 mSv/y; and are above the world average limit of 0.3 mSv/y. The mean of the total ELCR are (3.038 ± 0.774) X 10"-"3, (3.529 ± 0.547) X 10"-"3, and (3.210 ± 0.748) X 10"-"3; and are above the world average limit of 0.29 X 10"-"3. Most values of ELCR computed in this work are >6.0 X 10"-"4 estimated to be the risk of fatal and weighted nonfatal health conditions over a lifetime (70 years) derived from the radiation dose of 0.1 mSv/y (WHO permissible limit for drinking water). Drinking water from these surveyed sources could impact negatively on the end users. (author)

  5. Risk assessment

    International Nuclear Information System (INIS)

    1983-01-01

    The report is in sections, entitled: preface; summary and conclusions; introduction (historical and organizational); estimating engineering risks (techniques of risk estimation and forms of expression of risk); laboratory experiments for estimation of biological risks; estimation of risk from observations on man (travel, medical procedures; occupations; sport); the perception of risks; (as an example of attitudes towards a single hazard, studies of nuclear power are considered among other topics in this section); risk management (estimation; perception; acceptability, analysis of risk, costs and benefits; safety standards; decision-making process; possible guidelines). (U.K.)

  6. Radiological assessment of the town of Edgemont

    International Nuclear Information System (INIS)

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

    1985-01-01

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

  7. Risk assessment on hazards for decommissioning safety of a nuclear facility

    International Nuclear Information System (INIS)

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

    2010-01-01

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

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

    International Nuclear Information System (INIS)

    Trueba Alonso, C.

    2005-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-12-15

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

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

    International Nuclear Information System (INIS)

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

    2016-01-01

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

  11. Radiological impact assessment in Malaysia using RESRAD computer code

    International Nuclear Information System (INIS)

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

    1999-01-01

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

  12. Citizenship approach to promote a radiological protection and risk assessment culture at the school level; educational project in Belarus and French schools

    International Nuclear Information System (INIS)

    Autret, J.C.; Josset, M.

    2006-01-01

    Full text of publication follows: In the framework of the international C.O.R.E. programme (Cooperation for Rehabilitation of living conditions in Chernobyl affected areas in Belarus), an educational project was launched in 2004 meant so that the pupils of the Bragin district schools (in the south east of Belarus) will get involved in learning the practice of a radiological culture. Since the damages of radioactivity are cumulative, it is important to reduce the inhabitants daily intake of radioactivity. In the daily life, the understanding of radioactivity issues and the current recommendations concerning food and the environment are not always applied and accessible to the public. By showing that monitoring could help them to reduce the dose of radioactive elements, this project aims at breaking a fatalistic turn of mind. A steady radioecological education is the key element in establishing a practical radiological culture within the population. This project is essentially centred on children who represent both the future generation and the most sensitive group among contaminated by the radioactive effect. Children represent also the best way to realise in -depth contact with the whole population. To facilitate the development of the educational projects, Belarus teams of teachers will receive in -depth expert training in cooperation of the local professionals which will enable them to become active participants in conceiving and carrying out their own educational projects. A more specific training, concerning radiation protection is also be implemented by our N.G.O., with the help of the local organisation Rastok Gesne (Sprout of Life N.G.O.). The pedagogic actions are based on a complete and active involvement of the children and within an interdisciplinary approach will make it possible to include the different activities linked to radiological culture, and more widely, all the other aspects of living in a contaminated area so as to be able to face the risk

  13. Radiological assessment of the Esk Estuary

    International Nuclear Information System (INIS)

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

    1993-01-01

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

  14. Malaysian experiences in radiological safety assessment on norm wastes

    International Nuclear Information System (INIS)

    Syed Hakimi Sakuma Syed Ahmad; Khairuddin Mohamad Kontol

    2000-01-01

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

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

    International Nuclear Information System (INIS)

    Deboodt, Pascal

    2002-01-01

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

  16. The way to inform the general public about radiological risks

    International Nuclear Information System (INIS)

    Artus, J.C.

    2002-01-01

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

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

    Science.gov (United States)

    Becker, Steven M

    2011-11-01

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

  18. Introduction to risk assessment

    International Nuclear Information System (INIS)

    Raina, V.M.

    2002-01-01

    This paper gives an introduction to risk assessment. It discusses the basic concepts of risk assessment, nuclear risk assessment process and products, the role of risk assessment products in nuclear safety assurance, the relationship between risk assessment and other safety analysis and risk assessment and safe operating envelope

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

    African Journals Online (AJOL)

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

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

    African Journals Online (AJOL)

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

  1. Radiological assessment of decommissioned nuclear facilities

    International Nuclear Information System (INIS)

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

    1976-01-01

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

  2. 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

  3. Quality assessment for radiological model parameters

    International Nuclear Information System (INIS)

    Funtowicz, S.O.

    1989-01-01

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

  4. 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

  5. Federal Radiological Monitoring and Assessment Center Phased Response Operations

    International Nuclear Information System (INIS)

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

    1999-01-01

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

  6. Challenges in Risk Assessment: Quantitative Risk Assessment

    OpenAIRE

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

    2016-01-01

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

  7. Radiological risks in an operational environment

    International Nuclear Information System (INIS)

    Castagnet, X.; Lafferrerie, C.; Amabile, J.C.; Cazoulat, A.; Laroche, P.

    2010-01-01

    A radiological hazard (e. g. a detonating dirty bomb or accidental radionuclide dispersion) leading to a large number of contaminated or irradiated people needing immediate medical assistance is one of the main threats our troops deployed in an operational environment are facing. Immediate first aid anyway shall take precedence over decontamination but the unique nature of these injuries necessitates specific medical knowledge and training. A contaminated victim needs a rapid -clinical physical and biological- medical evaluation which will determine the amount of required medical support. A person with external contamination needs to be rapidly cleansed to limit spreading surface burns as well as limiting the possible contamination internally spreading into the body. A person with internal contamination requires rapid decontamination at the wound point and antidotes to internally cleanse the body. In France, the Military Health Service has developed a centre of expertise at the Percy military hospital near Paris which is geared up to deal with the victims of radiological attacks. It also has a mobile laboratory equipped with full radio toxicology equipment and body dosimeters to enable rapid and effective results when required. (authors)

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

    African Journals Online (AJOL)

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

  9. Dosimetry on the radiological risks prevention in radiotherapy

    International Nuclear Information System (INIS)

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

    2014-08-01

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

  10. 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

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

    International Nuclear Information System (INIS)

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

    1999-01-01

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

  12. Radiological Impact Assessment in Disposal of Treated Sludge

    International Nuclear Information System (INIS)

    Khairuddin Mohamad Kontol; Ismail Sulaiman; Faizal Azrin Abdul Razalim

    2015-01-01

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

  13. Benefit/risk comparisons in diagnostic radiology

    International Nuclear Information System (INIS)

    Oosterkamp, W.J.

    1976-01-01

    Benefit and risks in radiodiagnostic examination, either with X-rays or with radioactive isotopes, can be expressed in restored health and health impaired by radiation or: lives saved and estimated lives lost as a result of genetic or somatic radiation damage. Published data on benefit-risk comparisons for mass stomach and chest surveys show a considerable benefit surplus. It is demonstrated that this is also true in the case of clinical examinations of the sick. Efforts should be concentrated on better ways and means to reduce the number of diagnostic errors. Risk estimates should be made as realistic as possible

  14. 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.)

  15. Uncertainties in environmental radiological assessment models and their implications

    International Nuclear Information System (INIS)

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

    1983-01-01

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

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

    International Nuclear Information System (INIS)

    2000-08-01

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

  17. Quantitative evaluation of risks for individuals in diagnostic radiology

    Energy Technology Data Exchange (ETDEWEB)

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

    1980-05-01

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

  18. Quantitative evaluation of risks for individuals in diagnostic radiology

    International Nuclear Information System (INIS)

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

    1980-01-01

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

  19. Radiological assessment. A textbook on environmental dose analysis

    International Nuclear Information System (INIS)

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

    1983-09-01

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

  20. Radiological assessment. A textbook on environmental dose analysis

    Energy Technology Data Exchange (ETDEWEB)

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

    1983-09-01

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

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

    International Nuclear Information System (INIS)

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

    1988-08-01

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

  2. Ethical aspects of radiological risks management

    International Nuclear Information System (INIS)

    Surgier, A.

    1996-01-01

    The complexity of the decisions to be taken by the radiation protection and safety authorities in the nuclear, medical, and industrial fields, as well as the importance of the risks involved, require consideration of the confidence that the public can have in the procedures and institutions associated with these decisions. The Technical Support Organisations that advise these authorities play an essential role in risk evaluation. They participate both in defining the scientific bases of the regulations and analysing the authorization request from the operators. The credibility of these bodies implies a clear separation between their function and that of the regulatory authorities and the operators. It also requires a guarantee of competence which is based on a high level research program and contacts with other similar organisations. The quality of the work carried out by the Technical Support Organisations must be regularly evaluated. One of the most important of the other conditions for ensuring the effectiveness of the expertise is its integration in a well defined decision-making procedure. The author has based this article on his experience as director of radiation protection in the IPSN (Institut de Protection et de Surete Nucleaire), an organisation formed in 1976, with a staff of 1,200 whose functions are to carry out research and provide expertise in health physics radioecology and nuclear safety. To reinforce its operating autonomy and authority, the status of the IPSN was thoroughly revised as strengthened in 1990. (Author)

  3. Methodology for assessing the radiological impact on environment

    International Nuclear Information System (INIS)

    Zhang Yongxing

    1988-01-01

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

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

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  5. Hepatitis Risk Assessment

    Science.gov (United States)

    ... please visit this page: About CDC.gov . Hepatitis Risk Assessment Recommend on Facebook Tweet Share Compartir Viral Hepatitis. Are you at risk? Take this 5 minute Hepatitis Risk Assessment developed ...

  6. Radiological risk of actinon (/sup 219/Rn)

    Energy Technology Data Exchange (ETDEWEB)

    Crawford, D.J.

    1981-12-01

    The research reported was designed to provide information on the following subjects: (1) development of the functional relations between exposure to the /sup 219/Rn decay chain and pertinent health effects; (2) specification of the circumstances under which a significant concentration of the decay chain may occur; (3) recommendation of an exposure standard which will provide protection of the public from significant elevation of health effects; and (4) an assessment of the impact of /sup 219/Rn on determinations of the concentration of the /sup 222/Rn decay chain and/or its precursors.

  7. Radiological risk of actinon (219Rn)

    International Nuclear Information System (INIS)

    Crawford, D.J.

    1981-12-01

    The research reported was designed to provide information on the following subjects: (1) development of the functional relations between exposure to the 219 Rn decay chain and pertinent health effects; (2) specification of the circumstances under which a significant concentration of the decay chain may occur; (3) recommendation of an exposure standard which will provide protection of the public from significant elevation of health effects; and (4) an assessment of the impact of 219 Rn on determinations of the concentration of the 222 Rn decay chain and/or its precursors

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

    International Nuclear Information System (INIS)

    Mueller, P.G.

    2000-01-01

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

  9. Teaching and Assessing Professionalism in Radiology Resident Education.

    Science.gov (United States)

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

    2017-05-01

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

  10. Quality assessment in radiological imaging methods

    International Nuclear Information System (INIS)

    Herstel, W.

    1985-01-01

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

  11. Assessment of the radiological impact of contaminated discharges

    Energy Technology Data Exchange (ETDEWEB)

    Sweeck, L; Zeevaert, T

    1996-09-18

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

  12. Cursory radiological assessment: Battelle Columbus Laboratory Decommissioning and Decontamination Project

    International Nuclear Information System (INIS)

    Smith, W.H.; Munyon, W.J.; Mosho, G.D.; Robinet, M.J.; Wynveen, R.A.

    1988-10-01

    This document reports on the results obtained from a cursory radiological assessment of various properties at the Battelle Columbus Laboratory, Columbia, Ohio. The cursory radiological assessment is part of a preliminary investigation for the Battelle Columbus Laboratory Decommissioning and Decontamination Project. The radiological assessment of Battelle Columbus Laboratory's two sites included conducting interior and exterior building surveys and collecting and analyzing air, sewer system, and soil samples. Direct radiological surveys were made of floor, wall, and overhead areas. Smear surveys were made on various interior building surfaces as well as the exterior building vents. Air samples were collected in select areas to determine concentrations of Rn-222, Rn-220, and Rn-219 daughters, in addition to any long-lived radioactive particulates. Radon-222 concentrations were continuously monitored over a 24-hr period at several building locations using a radon gas monitoring system. The sanitary sewer systems at King Avenue, West Jefferson-North, and West Jefferson-South were each sampled at select locations. All samples were submitted to the Argonne Analytical Chemistry Laboratory for various radiological and chemical analyses. Environmental soil corings were taken at both the King Avenue and West Jefferson sites to investigate the potential for soil contamination within the first 12-inches below grade. Further subsurface investigations at the West Jefferson-North and West Jefferson-South areas were conducted using soil boring techniques. 4 refs., 10 figs., 10 tabs

  13. Radiological risk assessment of isotope laboratories according to the requirements of the radiation protection ordinance and the protective labour legislation; Beurteilung des radiologischen Risikos von Isotopenlaboratorien nach den Vorgaben der Strahlenschutzverordnung und den Richtlinien fuer Arbeitssicherheit

    Energy Technology Data Exchange (ETDEWEB)

    Stuerm, R.P. [SafPro AG, Ausbildung und Beratung in Strahlenschutz, Basel (Switzerland); Kuster, M. [Novartis International AG, Corporate Health, Safety and Environment, Basel (Switzerland); Traub, K. [Novartis Pharma AG, Zentralstelle fuer Strahlenschutz, Basel (Switzerland)

    2001-07-01

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

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

    International Nuclear Information System (INIS)

    Augustine, K.; McCoubrie, P.; Wilkinson, J.R.; McKnight, L.

    2010-01-01

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

  15. Dutch Risk Assessment tools

    NARCIS (Netherlands)

    Venema, A.

    2015-01-01

    The ‘Risico- Inventarisatie- en Evaluatie-instrumenten’ is the name for the Dutch risk assessment (RA) tools. A RA tool can be used to perform a risk assessment including an evaluation of the identified risks. These tools were among the first online risk assessment tools developed in Europe. The

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

    International Nuclear Information System (INIS)

    Nielsen, E.C.

    2005-01-01

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

  17. Federal Radiological Monitoring and Assessment Center Analytical Response

    International Nuclear Information System (INIS)

    Nielsen, E.C.

    2003-01-01

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

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

    International Nuclear Information System (INIS)

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

    2012-01-01

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

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

    International Nuclear Information System (INIS)

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

    1995-01-01

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

  20. Documentation of in-training assessment for radiology trainees

    International Nuclear Information System (INIS)

    Long, Gillian

    2001-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-07-01

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

  2. 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

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

    Directory of Open Access Journals (Sweden)

    Jongtae Jeong

    2016-12-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-12-15

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

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

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  6. Role of the Federal Radiological Monitoring and Assessment Center (FRMAC) following a radiological accident

    International Nuclear Information System (INIS)

    Doyle, J.F. III.

    1986-01-01

    The Federal Radiological Emergency Response Plan (FRERP) calls for the Department of Energy to establish a Federal Radiological Monitoring and Assessment Center (FRMAC) immediately following a major radiological accident to coordinate all federal off-site monitoring efforts in support of the State and the Cognizant Federal Agency (CFA) for the facility or material involved in the accident. Some accidents are potentailly very complex and may require hundreds of radiation specialists to ensure immediate protection of the public and workers in the area, and to identify priorities for the Environmental Protection Agency (EPA) long-term efforts once the immediate protective actions have been carried out. The FRMAC provides a working environment with today's high technology tools (i.e., communication, computers, management procedures, etc.) to assure that the State and CFA decision makers have the best possible information in a timely manner on which to act. The FRMAC planners also recognize an underlying responsibility to continuously document such operations in order to provide the State, the CFA, and the EPA the technical information they will require for long term assessments. In addition, it is fully recognized that information collected and actions taken by the FRMAC will be subjected to the same scrutiny as other parts of the accident and the overall response

  7. Preliminary radiological assessments of low-level waste repositories

    International Nuclear Information System (INIS)

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

    1988-06-01

    Preliminary assessments of the post-closure radiological impact from the disposal of low-level radioactive wastes in shallow engineered facilities at four sites are presented. This provides a framework to practice and refine a methodology that could be used, on behalf of the Department, for independent assessment of any similar proposal from Nirex. Information and methodological improvements that would be required are identified. (author)

  8. Radiological Assessments and Enhanced Natural Radioactivity

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  9. Radiological risks of transports to central waste management facilities

    International Nuclear Information System (INIS)

    Lange, F.

    1997-01-01

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

  10. Risks from dental radiology; Os riscos provenientes da radiologia odontologica

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-10-01

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

  11. Occuptional radiation exposures and thyroid cancer risk among radiologic technologists

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-04-15

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

  12. Occuptional radiation exposures and thyroid cancer risk among radiologic technologists

    International Nuclear Information System (INIS)

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

    2016-01-01

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

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

    Science.gov (United States)

    Durante, Marco; Pugliese, Mariagabriella

    2002-01-01

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

  14. Models and parameters for environmental radiological assessments

    International Nuclear Information System (INIS)

    Miller, C.W.

    1984-01-01

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

  15. Models and parameters for environmental radiological assessments

    Energy Technology Data Exchange (ETDEWEB)

    Miller, C W [ed.

    1984-01-01

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

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

    International Nuclear Information System (INIS)

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

    1995-06-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-06-01

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

  18. Assessment of radiological technologist health condition by Todai health index

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ham Gyum [Ansan College, Ansan (Korea, Republic of); Kim, Wha Sun [College of Medicine, Hanyang Univ., Seoul (Korea, Republic of)

    2001-04-01

    The purpose of this study was to examine the general health status of radiological technologists by using Todai Health Index(THI) that has been employed as a standard health assessment tool for a specific group. The subjects in this study were 800 radiological technologists who were working in clinics, hospitals and university hospitals in and around Seoul and in some provincial cities. A survey was conducted directly or by mail in June and July, 2001. And the response rate was 68%. Using THI, the following findings were acquired: 1. By gender, both male and female radiological technologists complained about multiple subjective symptom(I) the most, And the women made more significant complaint of eight items including irregular life. 2. By age group, the radiological technologists whose age ranged from 20 to 24 got higher marks in most of the items, including multiple subjective symptom(I) and symptoms related to eyes and skin. 3. For career, those who had worked for a year or less or for one to five years got higher marks in most of the items. 4. Concerning marital status, the unmarried people complained about many items more, and the married people's symptom was more associated with live scale(L). 5. By the type of medical institution, the radiological technologists in the university hospitals got higher marks in two items including aggressiveness(F), but those in the clinics complained about the others more. 6. Regarding a place of service, there were little differences between the radiological technologists in basement and on the ground.

  19. Assessment of radiological technologist health condition by Todai health index

    International Nuclear Information System (INIS)

    Kim, Ham Gyum; Kim, Wha Sun

    2001-01-01

    The purpose of this study was to examine the general health status of radiological technologists by using Todai Health Index(THI) that has been employed as a standard health assessment tool for a specific group. The subjects in this study were 800 radiological technologists who were working in clinics, hospitals and university hospitals in and around Seoul and in some provincial cities. A survey was conducted directly or by mail in June and July, 2001. And the response rate was 68%. Using THI, the following findings were acquired: 1. By gender, both male and female radiological technologists complained about multiple subjective symptom(I) the most, And the women made more significant complaint of eight items including irregular life. 2. By age group, the radiological technologists whose age ranged from 20 to 24 got higher marks in most of the items, including multiple subjective symptom(I) and symptoms related to eyes and skin. 3. For career, those who had worked for a year or less or for one to five years got higher marks in most of the items. 4. Concerning marital status, the unmarried people complained about many items more, and the married people's symptom was more associated with live scale(L). 5. By the type of medical institution, the radiological technologists in the university hospitals got higher marks in two items including aggressiveness(F), but those in the clinics complained about the others more. 6. Regarding a place of service, there were little differences between the radiological technologists in basement and on the ground

  20. 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

  1. Chemical and radiological vulnerability assessment in urban areas

    Directory of Open Access Journals (Sweden)

    Stojanović Božidar

    2006-01-01

    Full Text Available Cities and towns are faced with various types of threat from the extraordinary events involving chemical and radiological materials as exemplified by major chemical accidents, radiological incidents, fires, explosions, traffic accidents, terrorist attacks, etc. On the other hand, many sensitive or vulnerable assets exist within cities, such as: settlements, infrastructures, hospitals, schools, churches, businesses, government, and others. Besides emergency planning, the land use planning also represents an important tool for prevention or reduction of damages on people and other assets due to unwanted events. This paper considers development of method for inclusion vulnerability assessment in land use planning with objective to assess and limit the consequences in cities of likely accidents involving hazardous materials. We made preliminary assessment of criticality and vulnerability of the assets within Belgrade city area in respect to chemical sites and transportation roads that can be exposed to chemical accidents, or terrorist attacks.

  2. Assessment of cardiovascular risk.

    LENUS (Irish Health Repository)

    Cooney, Marie Therese

    2010-10-01

    Atherosclerotic cardiovascular disease (CVD) is the most common cause of death worldwide. Usually atherosclerosis is caused by the combined effects of multiple risk factors. For this reason, most guidelines on the prevention of CVD stress the assessment of total CVD risk. The most intensive risk factor modification can then be directed towards the individuals who will derive the greatest benefit. To assist the clinician in calculating the effects of these multiple interacting risk factors, a number of risk estimation systems have been developed. This review address several issues regarding total CVD risk assessment: Why should total CVD risk be assessed? What risk estimation systems are available? How well do these systems estimate risk? What are the advantages and disadvantages of the current systems? What are the current limitations of risk estimation systems and how can they be resolved? What new developments have occurred in CVD risk estimation?

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

    International Nuclear Information System (INIS)

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

    1992-01-01

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

  4. GM Risk Assessment

    Science.gov (United States)

    Sparrow, Penny A. C.

    GM risk assessments play an important role in the decision-making process surrounding the regulation, notification and permission to handle Genetically Modified Organisms (GMOs). Ultimately the role of a GM risk assessment will be to ensure the safe handling and containment of the GMO; and to assess any potential impacts on the environment and human health. A risk assessment should answer all ‘what if’ scenarios, based on scientific evidence.

  5. The radiological assessment system for consequence analysis - RASCAL

    International Nuclear Information System (INIS)

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

    1996-01-01

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

  6. Radiological interpretation 2020: Toward quantitative image assessment

    International Nuclear Information System (INIS)

    Boone, John M.

    2007-01-01

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

  7. ZZ RADDECAY, Decay Data Library for Radiological Assessment

    International Nuclear Information System (INIS)

    2000-01-01

    Description of program or function: - Format: special format defined in documentation. - Nuclides: 500 nuclides of interest in the nuclear fuel cycle, environmental problems, nuclear medicine, fusion reactor technology, and radiological protection assessment. - Origin: DLC-80/DRALIST. ZZ-RADDECAY is a data library of half-lives, radioactive daughter nuclides, probabilities per decay and decay product energies for alpha particles, positrons, electrons, X-rays, and gamma-rays. The current data base contains approximately 500 nuclides of interest in the nuclear fuel cycle, environmental problems, nuclear medicine, fusion reactor technology, and radiological protection assessment. RADIATION DECAY VERSION 2 March 1997: This application is being provided by Aptec as 'Freeware' with permission of the author Mr. Charles Hacker, Engineering and Applied Science, Griffith University, Australia

  8. An attempt to evaluate the risks associated with radiological terror

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  9. 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

  10. Strategic Risk Assessment

    Science.gov (United States)

    Derleth, Jason; Lobia, Marcus

    2009-01-01

    This slide presentation provides an overview of the attempt to develop and demonstrate a methodology for the comparative assessment of risks across the entire portfolio of NASA projects and assets. It includes information about strategic risk identification, normalizing strategic risks, calculation of relative risk score, and implementation options.

  11. CP-50 calibration facility radiological safety assessment document

    International Nuclear Information System (INIS)

    Chilton, M.W.; Hill, R.L.; Eubank, B.F.

    1980-03-01

    The CP-50 Calibration Facility Radiological Safety Assessment document, prepared at the request of the Nevada Operations Office of the US Department of Energy to satisfy provisions of ERDA Manual Chapter 0531, presents design features, systems controls, and procedures used in the operation of the calibration facility. Site and facility characteristics and routine and non-routine operations, including hypothetical incidents or accidents are discussed and design factors, source control systems, and radiation monitoring considerations are described

  12. 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

  13. 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.

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

    International Nuclear Information System (INIS)

    Diaz de la Cruz, F.

    1979-01-01

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

  15. Ecological risk assessment

    National Research Council Canada - National Science Library

    Suter, Glenn W; Barnthouse, L. W. (Lawrence W)

    2007-01-01

    Ecological risk assessment is commonly applied to the regulation of chemicals, the remediation of contaminated sites, the monitoring of importation of exotic organisms, the management of watersheds...

  16. Risk Assessment Overview

    Science.gov (United States)

    Prassinos, Peter G.; Lyver, John W., IV; Bui, Chinh T.

    2011-01-01

    Risk assessment is used in many industries to identify and manage risks. Initially developed for use on aeronautical and nuclear systems, risk assessment has been applied to transportation, chemical, computer, financial, and security systems among others. It is used to gain an understanding of the weaknesses or vulnerabilities in a system so modification can be made to increase operability, efficiency, and safety and to reduce failure and down-time. Risk assessment results are primary inputs to risk-informed decision making; where risk information including uncertainty is used along with other pertinent information to assist management in the decision-making process. Therefore, to be useful, a risk assessment must be directed at specific objectives. As the world embraces the globalization of trade and manufacturing, understanding the associated risk become important to decision making. Applying risk assessment techniques to a global system of development, manufacturing, and transportation can provide insight into how the system can fail, the likelihood of system failure and the consequences of system failure. The risk assessment can identify those elements that contribute most to risk and identify measures to prevent and mitigate failures, disruptions, and damaging outcomes. In addition, risk associated with public and environment impact can be identified. The risk insights gained can be applied to making decisions concerning suitable development and manufacturing locations, supply chains, and transportation strategies. While risk assessment has been mostly applied to mechanical and electrical systems, the concepts and techniques can be applied across other systems and activities. This paper provides a basic overview of the development of a risk assessment.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-04-15

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

  18. Biosafety Risk Assessment Methodology

    Energy Technology Data Exchange (ETDEWEB)

    Caskey, Susan Adele [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). International Biological Threat Reduction Program; Gaudioso, Jennifer M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). International Biological Threat Reduction Program; Salerno, Reynolds Mathewson [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). International Biological Threat Reduction Program; Wagner, Stefan M. [Public Health Agency of Canada, Winnipeg, MB (Canada). Canadian Science Centre for Human and Animal Health (CSCHAH); Shigematsu, Mika [National Inst. of Infectious Diseases (NIID), Tokyo (Japan); Risi, George [Infectious Disease Specialists, P.C, Missoula, MT (United States); Kozlovac, Joe [US Dept. of Agriculture (USDA)., Beltsville, MD (United States); Halkjaer-Knudsen, Vibeke [Statens Serum Inst., Copenhagen (Denmark); Prat, Esmeralda [Bayer CropScience, Monheim am Rhein (Germany)

    2010-10-01

    Laboratories that work with biological agents need to manage their safety risks to persons working the laboratories and the human and animal community in the surrounding areas. Biosafety guidance defines a wide variety of biosafety risk mitigation measures, which include measures which fall under the following categories: engineering controls, procedural and administrative controls, and the use of personal protective equipment; the determination of which mitigation measures should be used to address the specific laboratory risks are dependent upon a risk assessment. Ideally, a risk assessment should be conducted in a manner which is standardized and systematic which allows it to be repeatable and comparable. A risk assessment should clearly define the risk being assessed and avoid over complication.

  19. Offshore risk assessment

    CERN Document Server

    Vinnem, Jan-Erik

    2014-01-01

      Offshore Risk Assessment was the first book to deal with quantified risk assessment (QRA) as applied specifically to offshore installations and operations. Risk assessment techniques have been used for more than three decades in the offshore oil and gas industry, and their use is set to expand increasingly as the industry moves into new areas and faces new challenges in older regions.   This updated and expanded third edition has been informed by a major R&D program on offshore risk assessment in Norway and summarizes research from 2006 to the present day. Rooted with a thorough discussion of risk metrics and risk analysis methodology,  subsequent chapters are devoted to analytical approaches to escalation, escape, evacuation and rescue analysis of safety and emergency systems.   Separate chapters analyze the main hazards of offshore structures: fire, explosion, collision, and falling objects as well as structural and marine hazards. Risk mitigation and control are discussed, as well as an illustrat...

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

    International Nuclear Information System (INIS)

    Angerstein, W.

    1995-01-01

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

  1. Assessing Expertise in Radiology : Evaluating and Improving the Assessment of Knowledge and Image Interpretation Skill

    NARCIS (Netherlands)

    Ravesloot, C.J.

    2016-01-01

    Aim: Expert radiologists are excellent image interpreters. Unfortunately, image interpretation errors are frequent even among experienced radiologists and not much is known about which factors lead to expertise. Increasing assessment quality can improve radiological performance. Progress tests can

  2. Radiological impact assessment of arc welding supplies rutile

    International Nuclear Information System (INIS)

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

    2013-01-01

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

  3. Benchmark problems for radiological assessment codes. Final report

    International Nuclear Information System (INIS)

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

    1983-09-01

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

  4. A radiological accident consequence assessment system for Hong Kong

    International Nuclear Information System (INIS)

    Wong, M.C.; Lam, H.K.

    1993-01-01

    An account is given of the Hong Kong Radiological Accident Consequence Assessment System which would be used to assess the potential consequences of an emergency situation involving atmospheric release of radioactive material. The system has the capability to acquire real-time meteorological information from the Observatory's network of automatic stations, synoptic stations in the nearby region as well as forecast data from numerical prediction models. The system makes use of these data to simulate the transport and dispersion of the released radioactive material. The effectiveness of protective action on the local population is also modeled. The system serves as a powerful aid in the protective action recommendation processes

  5. Patients exposure assessment for radiographic procedures in diagnostic radiology

    International Nuclear Information System (INIS)

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

    2007-01-01

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

  6. Radiological emergency assessment of local decision support system

    International Nuclear Information System (INIS)

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

    2003-01-01

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

  7. Operational risk assessment.

    Science.gov (United States)

    McKim, Vicky L

    2017-06-01

    In the world of risk management, which encompasses the business continuity disciplines, many types of risk require evaluation. Financial risk is most often the primary focus, followed by product and market risks. Another critical area, which typically lacks a thorough review or may be overlooked, is operational risk. This category encompasses many risk exposure types including those around building structures and systems, environmental issues, nature, neighbours, clients, regulatory compliance, network, data security and so on. At times, insurance carriers will assess internal hazards, but seldom do these assessments include more than a cursory look at other types of operational risk. In heavily regulated environments, risk assessments are required but may not always include thorough assessments of operational exposures. Vulnerabilities may linger or go unnoticed, only to become the catalyst for a business disruption at a later time, some of which are so severe that business recovery becomes nearly impossible. Businesses may suffer loss of clients as the result of a prolonged disruption of services. Comprehensive operational risk assessments can assist in identifying such vulnerabilities, exposures and threats so that the risk can be minimised or removed. This paper lays out how an assessment of this type can be successfully conducted.

  8. Risk assessment [Chapter 9

    Science.gov (United States)

    Dennis S. Ojima; Louis R. Iverson; Brent L. Sohngen; James M. Vose; Christopher W. Woodall; Grant M. Domke; David L. Peterson; Jeremy S. Littell; Stephen N. Matthews; Anantha M. Prasad; Matthew P. Peters; Gary W. Yohe; Megan M. Friggens

    2014-01-01

    What is "risk" in the context of climate change? How can a "risk-based framework" help assess the effects of climate change and develop adaptation priorities? Risk can be described by the likelihood of an impact occurring and the magnitude of the consequences of the impact (Yohe 2010) (Fig. 9.1). High-magnitude impacts are always...

  9. Chemical Risk Assessment

    Science.gov (United States)

    This course is aimed at providing an overview of the fundamental guiding principles and general methods used in chemical risk assessment. Chemical risk assessment is a complex and ever-evolving process. These principles and methods have been organized by the National Research Cou...

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

    International Nuclear Information System (INIS)

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

    2011-01-01

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

  11. Overview of risk assessment

    International Nuclear Information System (INIS)

    Rimington, J.D.

    1992-01-01

    The paper begins by defining some terms, and then refer to a number of technical and other difficulties. Finally it attempts to set out why risk assessment is important and what its purposes are. 2) First, risk and risk assessment - what are they?. 3) Risk is a subject of universal significance. Life is very uncertain, and we can achieve no object or benefit in it except by approaching nearer to particular hazards which lie between us and our objects. That approach represents acceptance of risk. 4) Risk assessment is a way of systematising our approach to hazard with a view to determining what is more and what is less risky. It helps us in the end to diminish our exposure while obtaining whatever benefits we have in mind, or to optimise the risks and the benefits

  12. Overview of risk assessment

    Energy Technology Data Exchange (ETDEWEB)

    Rimington, J D [Health and Safety Executive (United Kingdom)

    1992-07-01

    The paper begins by defining some terms, and then refer to a number of technical and other difficulties. Finally it attempts to set out why risk assessment is important and what its purposes are. 2) First, risk and risk assessment - what are they?. 3) Risk is a subject of universal significance. Life is very uncertain, and we can achieve no object or benefit in it except by approaching nearer to particular hazards which lie between us and our objects. That approach represents acceptance of risk. 4) Risk assessment is a way of systematising our approach to hazard with a view to determining what is more and what is less risky. It helps us in the end to diminish our exposure while obtaining whatever benefits we have in mind, or to optimise the risks and the benefits.

  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. Radiation monitoring systems and methodologies for radiological impact assessment

    International Nuclear Information System (INIS)

    Chaudhury, Probal

    2016-01-01

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

  16. State of risk assessment

    International Nuclear Information System (INIS)

    Conrad, J.

    1978-03-01

    In view of the growing importance assumed in recent years by scientific work on the calculation, quantification, evaluation and acceptance as well as behavior in the face of risks in general and more specifically, the risks of large industrial plants, the report attempts to provide a survey of the current situation, results and evaluation of this new branch of research, risk assessment. The emphasis of the report is on the basic discussion and criticism of the theoretical and methodological approaches used in the field of risk assessment (section 3). It is concerned above all with - methodical problems of determining and quantifying risks (3.1) - questions of the possibility of risk evaluation and comp arison (3.1, 3.2) - the premises of normative and empirical studies on decision making under risk (3.2, 3.3) - investigations into society's acceptance of risks involved in the introduction of new technologies (3.4) - attempts to combine various aspects of the field of risk assessment in a unified concept (3.5, 3.6, 3.7). Because risk assessment is embedded in the framework of decision theory and technology assessment, it can be implicitly evaluated at a more general level within this framework, as far as its possibilities and weaknesses of method and application are concerned (section 4). Sections 2 and 5 deal with the social context of origin and utilization of risk assessment. Finally, an attempt is made at a summary indicating the possible future development of risk assessment. (orig./HP) [de

  17. Patient caries risk assessment

    DEFF Research Database (Denmark)

    Twetman, Svante; Fontana, Margherita

    2009-01-01

    Risk assessment is an essential component in the decision-making process for the correct prevention and management of dental caries. Multiple risk factors and indicators have been proposed as targets in the assessment of risk of future disease, varying sometimes based on the age group at which...... they are targeted. Multiple reviews and systematic reviews are available in the literature on this topic. This chapter focusses primarily on results of reviews based on longitudinal studies required to establish the accuracy of caries risk assessment. These findings demonstrate that there is a strong body...... of evidence to support that caries experience is still, unfortunately, the single best predictor for future caries development. In young children, prediction models which include a variety of risk factors seem to increase the accuracy of the prediction, while the usefulness of additional risk factors...

  18. 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

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

    International Nuclear Information System (INIS)

    Campos, M.P. de.

    1994-01-01

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

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

    International Nuclear Information System (INIS)

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

    1984-10-01

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

  1. 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

  2. GAR Global Risk Assessment

    Science.gov (United States)

    Maskrey, Andrew; Safaie, Sahar

    2015-04-01

    Disaster risk management strategies, policies and actions need to be based on evidence of current disaster loss and risk patterns, past trends and future projections, and underlying risk factors. Faced with competing demands for resources, at any level it is only possible to priorities a range of disaster risk management strategies and investments with adequate understanding of realised losses, current and future risk levels and impacts on economic growth and social wellbeing as well as cost and impact of the strategy. The mapping and understanding of the global risk landscape has been greatly enhanced by the latest iteration of the GAR Global Risk Assessment and the objective of this submission is to present the GAR global risk assessment which contributed to Global Assessment Report (GAR) 2015. This initiative which has been led by UNISDR, was conducted by a consortium of technical institutions from around the world and has covered earthquake, cyclone, riverine flood, and tsunami probabilistic risk for all countries of the world. In addition, the risks associated with volcanic ash in the Asia-Pacific region, drought in various countries in sub-Saharan Africa and climate change in a number of countries have been calculated. The presentation will share thee results as well as the experience including the challenges faced in technical elements as well as the process and recommendations for the future of such endeavour.

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

    International Nuclear Information System (INIS)

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

    2012-01-01

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

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

    International Nuclear Information System (INIS)

    2011-01-01

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

  5. Review at Bikini Atoll. Assessing radiological conditions at Bikini Atoll and the prospects for resettlement

    International Nuclear Information System (INIS)

    Stegnar, P.

    1998-01-01

    Some testing during the development of the atomic bomb was done in countries that do not have the infrastructure and expertise for evaluating any associated radiation risks. In such cases, outside expertise is needed to obtain independent advice about the radiological situation caused by residual radioactive material from nuclear testing. The IAEA has been requested by the governments of a number of its Member States to provide assistance in this context. Among the former nuclear test sites which the IAEA has reviewed is the Bikini Atoll of the Marshall Islands. Based on its review, the IAEA Advisory Group determined that no further corroboration of the measurements and assessments of the radiological conditions at Bikini Atoll is necessary. The data that have been collected are of sufficient quality to allow an appropriate evaluation to be performed. The limited IAEA monitoring of the area provided a good quality assurance verification of the previously collected data. It was recommended that Bikini Island should not be permanently resettled under the present radiological conditions. This recommendation was based on the assumption that persons resettling on the island would consume a diet of entirely locally produced food. The radiological data support that if a diet of this type were permitted, it could lead to an annual effective dose of about 15 mSv. This level was judged to require intervention of some type for radiation protection purposes

  6. Radiological assessment for bauxite mining and alumina refining.

    Science.gov (United States)

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

    2013-01-01

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

  7. Sovereign default risk assessment

    NARCIS (Netherlands)

    Rijken, H.A.; Altman, E.I.

    2013-01-01

    We propose a new approach toward assessing sovereign risk by examining rigorously the health and aggregate default risk of a nation's private corporate sector. Models can be utilised to measure the probability of default of the non-financial sector cumulatively for five years, both as an absolute

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

    International Nuclear Information System (INIS)

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

    1996-01-01

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

  9. Risk assessment of radiation carcinogenesis

    International Nuclear Information System (INIS)

    Kai, Michiaki

    2012-01-01

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

  10. Efficient radiological assessment of the internal snapping hip syndrome

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  11. Citizen perceptions of risks associated with moving radiological waste

    International Nuclear Information System (INIS)

    McBeth, M.K.; Oakes, A.S.

    1996-01-01

    Much has been written about public support or opposition to the siting of hazardous waste facilities and more generally about concern for radioactive contamination. Much less has been written about the perceived risks of citizens' specific concerns about the transportation of radiological waste to temporary or permanent sites. This study reviews the existing literature in the area and presents new data on the subject from an Idaho survey. The new data indicates: (1) age, gender, and knowledge are the key variables predicting opposition to the transportation of such waste, (2) the primary concern among the opposing and unsure public is the planned use of trucks to move the TRU waste, and (3) respondents have high degrees of trust in officials who make decisions based on technical knowledge, are charged with the safety of transporting TRU waste, and who respond to mishaps. These attitudes need to be understood by policy makers and administrators when designing and implementing waste-transportation programs. 19 refs., 4 tabs

  12. CEA: risk management assessment 2011

    International Nuclear Information System (INIS)

    Bigot, Bernard; Bonnevie, Edwige; Maillot, Bernard

    2012-01-01

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

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

    Science.gov (United States)

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

    2018-01-09

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

  14. An Assessment of the radiological vulnerability for Spanish soils

    International Nuclear Information System (INIS)

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

    2000-01-01

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

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

    International Nuclear Information System (INIS)

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

    1993-09-01

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

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

    International Nuclear Information System (INIS)

    Qiu Guohua

    2008-01-01

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

  17. Preoperative radiological assessment of children with pectus excavatum

    International Nuclear Information System (INIS)

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

    2005-01-01

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

  18. The Generalised Ecosystem Modelling Approach in Radiological Assessment

    International Nuclear Information System (INIS)

    Klos, Richard

    2008-03-01

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

  19. The Generalised Ecosystem Modelling Approach in Radiological Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Klos, Richard

    2008-03-15

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

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

    International Nuclear Information System (INIS)

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

    2012-01-01

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

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

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  2. Safety analysis and risk assessment handbook

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  3. Chlorine transportation risk assessment

    International Nuclear Information System (INIS)

    Lautkaski, Risto; Mankamo, Tuomas.

    1977-02-01

    An assessment has been made on the toxication risk of the population due to the bulk rail transportation of liquid chlorine in Finland. Fourteen typical rail accidents were selected and their probability was estimated using the accident file of the Finnish State Railways. The probability of a chlorine leak was assessed for each type of accident separately using four leak size categories. The assessed leakage probability was dominated by station accidents, especially by collisions of a chlorine tanker and a locomotive. Toxication hazard areas were estimated for the leak categories. A simple model was constructed to describe the centring of the densely populated areas along the railway line. A comparison was made between the obtained risk and some other risks including those due to nuclear reactor accidents. (author)

  4. Assessment of fracture risk

    International Nuclear Information System (INIS)

    Kanis, John A.; Johansson, Helena; Oden, Anders; McCloskey, Eugene V.

    2009-01-01

    Fractures are a common complication of osteoporosis. Although osteoporosis is defined by bone mineral density at the femoral neck, other sites and validated techniques can be used for fracture prediction. Several clinical risk factors contribute to fracture risk independently of BMD. These include age, prior fragility fracture, smoking, excess alcohol, family history of hip fracture, rheumatoid arthritis and the use of oral glucocorticoids. These risk factors in conjunction with BMD can be integrated to provide estimates of fracture probability using the FRAX tool. Fracture probability rather than BMD alone can be used to fashion strategies for the assessment and treatment of osteoporosis.

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

    International Nuclear Information System (INIS)

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

    1993-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-03-15

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

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

    Science.gov (United States)

    Divrik Gökçe, Senem; Coşkun, Melek

    2012-01-01

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

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

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  9. 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)

  10. Radiological Instrumentation Assessment for King County Wastewater Treatment Division

    International Nuclear Information System (INIS)

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

    2005-01-01

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

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

    International Nuclear Information System (INIS)

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

    1980-04-01

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

  12. Application of probabilistic risk assessment to reprocessing

    International Nuclear Information System (INIS)

    Perkins, W.C.

    1984-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-07-01

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

  14. Concerning ethical risk assessment

    International Nuclear Information System (INIS)

    Boeckle, F.

    1991-01-01

    After a fundamental consideration of the concept of responsibility and 'long-term responsibility' for late sequelae, the problems of an ehtical assessment of risks were illustrated: The concept of risk itself poses three problems - predicting the probability of occurrence, assessing the damage = subjective classification of the degree of damage, determining whether the advantages outweigh the risks. It is not possible to weigh the advantages and risks against each other without assessing the goals and the priorities which have been set. Here ethics is called for, because it concerns itself with the reasonableness of evaluative decisions. Its task is to enable us to become aware of and comprehend our system of values in all of its complexity in reference to real life. Ethics can only fulfill its task if it helps us to adopt an integral perspective, i.e. if it centers on the human being. 'One must assess all technical and economic innovations in terms of whether they are beneficial to the development of mankind on a long-term basis. They are only to be legitimized insofar as they prove themselves to be a means of liberating mankind and contributing to his sense of dignity and identity, as a means of bringing human beings together and encouraging them to care for one another, and as a means of protecting the natural basis of our existence. (orig./HSCH) [de

  15. Radiological risk of building materials using homemade airtight radon chamber

    International Nuclear Information System (INIS)

    Norafatin Khalid; Amran Abdul Majid; Redzuwan Yahaya; Muhammad Samudi Yasir

    2013-01-01

    Full-text: Soil based building materials known to contain various amounts of natural radionuclide mainly 238 U and 232 Th series and 40 K. In general most individuals spend 80 % of their time indoors and the natural radioactivity in building materials is a main source of indoor radiation exposure. The internal exposure due to building materials in dwellings and workplaces is mainly caused by the activity concentrations of short lived 222 Radon and its progenies which arise from the decay of 226 Ra. In this study, the indoor radon concentration emanating from cement brick, red-clay brick, gravel aggregate and Portland cement samples were measured in a homemade airtight radon chamber using continuous radon monitor 1029 model of Sun Nuclear. Radon monitor were left in the chamber for 96 hours with an hour counting time interval. From the result, the indoor radon concentrations for cement brick, red-clay brick, gravel aggregate and Portland cement samples determined were 396 Bq m -3 , 192 Bq m -3 , 176 Bq m -3 and 28 Bq m -3 , respectively. The result indicates that the radon concentration in the studied building materials have more than 100 Bq m -3 for example higher than the WHO action level except for Portland cement sample. The calculated annual effective dose for cement brick, red-clay brick, gravel aggregate and Portland cement samples were determined to be 10 mSv y -1 , 4.85 mSv y -1 , 4.44 mSv y -1 and 0.72 mSv y -1 , respectively. This study showed that all the calculated effective doses generated from indoor radon to dwellers or workers were in the range of limit recommended ICRP action levels for example 3 - 10 mSv y -1 . As consequences, the radiological risk for the dwellers in terms of fatal lifetime cancer risk per million for cement brick, red-clay brick, gravel aggregate and Portland cement were calculated to be 550, 267, 244 and 40 persons respectively. (author)

  16. Radiological risk of building materials using homemade airtight radon chamber

    International Nuclear Information System (INIS)

    Khalid, Norafatin; Majid, Amran Ab.; Yahaya, Redzuwan; Yasir, Muhammad Samudi

    2014-01-01

    Soil based building materials known to contain various amounts of natural radionuclide mainly 238 U and 232 Th series and 40 K. In general most individuals spend 80% of their time indoors and the natural radioactivity in building materials is a main source of indoor radiation exposure. The internal exposure due to building materials in dwellings and workplaces is mainly caused by the activity concentrations of short lived 222 Radon and its progenies which arise from the decay of 226 Ra. In this study, the indoor radon concentration emanating from cement brick, red-clay brick, gravel aggregate and Portland cement samples were measured in a homemade airtight radon chamber using continuous radon monitor 1029 model of Sun Nuclear. Radon monitor were left in the chamber for 96 hours with an hour counting time interval. From the result, the indoor radon concentrations for cement brick, red-clay brick, gravel aggregate and Portland cement samples determined were 396 Bq m −3 , 192 Bq m −3 , 176 Bq m −3 and 28 Bq m −3 , respectively. The result indicates that the radon concentration in the studied building materials have more than 100 Bq m −3 i.e. higher than the WHO action level except for Portland cement sample. The calculated annual effective dose for cement brick, red-clay brick, gravel aggregate and Portland cement samples were determined to be 10 mSv y −1 , 4.85 mSv y −1 , 4.44 mSv y −1 and 0.72 mSv y −1 , respectively. This study showed that all the calculated effective doses generated from indoor radon to dwellers or workers were in the range of limit recommended ICRP action levels i.e. 3 - 10 mSv y −1 . As consequences, the radiological risk for the dwellers in terms of fatal lifetime cancer risk per million for cement brick, red-clay brick, gravel aggregate and Portland cement were calculated to be 550, 267, 244 and 40 persons respectively

  17. Methodology of environmental risk assessment management

    Directory of Open Access Journals (Sweden)

    Saša T. Bakrač

    2012-04-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-05-01

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

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

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  20. Radiological assessment of an area with uranium residual material

    International Nuclear Information System (INIS)

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

    2008-01-01

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

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

    International Nuclear Information System (INIS)

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

    1996-09-01

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

  2. Risk assessment: 'A consumer's perspective'

    Energy Technology Data Exchange (ETDEWEB)

    Waterhouse, Rachel [Consumer' s Association, Health and Safety Commission (United Kingdom)

    1992-07-01

    The paper assesses the concept of risk, risk assessment and tolerability of risk from consumer point of view. Review of existing UK and EC directives on certain products and appliances is also covered.

  3. Risk assessment: 'A consumer's perspective'

    International Nuclear Information System (INIS)

    Waterhouse, Rachel

    1992-01-01

    The paper assesses the concept of risk, risk assessment and tolerability of risk from consumer point of view. Review of existing UK and EC directives on certain products and appliances is also covered

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

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  5. Improving Site-Specific Radiological Performance Assessments - 13431

    International Nuclear Information System (INIS)

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

    2013-01-01

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

  6. Improving Site-Specific Radiological Performance Assessments - 13431

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

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

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

    International Nuclear Information System (INIS)

    1996-02-01

    In the event of a major radiological emergency, 17 federal agencies with various statutory responsibilities have agreed to coordinate their efforts at the emergency scene under the umbrella of the Federal Radiological Emergency Response plan (FRERP). This cooperative effort will assure the designated Lead Federal Agency (LFA) and the state(s) that all federal radiological assistance fully supports their efforts to protect the public. The mandated federal cooperation ensures that each agency can obtain the data critical to its specific responsibilities. This Overview of the Federal Radiological Monitoring and Assessment Center (FRMAC) Operations describes the FRMAC response activities to a major radiological emergency. It also describes the federal assets and subsequent operational activities which provide federal radiological monitoring and assessment of the off-site areas. These off-site areas may include one or more affected states

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

    International Nuclear Information System (INIS)

    1993-09-01

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

  9. Integral risk assessment

    International Nuclear Information System (INIS)

    Chakraborty, S.; Yadigaroglu, G.

    1991-01-01

    The series of lectures which forms the basis of this book and took place in the winter of 1989/90 at the ETH in Zuerich were held for the purpose of discussing the stage of development of our system of ethics in view of the extremely fast pace of technological progress and the risks which accompany it. Legal, psychological and political aspects of the problem were examined, but the emphasis was placed on ethical aspects. The effects which are examined in conventional risk analyses can be considered as a part of the ethical and social aspects involved, and in turn, the consideration of ethical and social aspects can be viewed as an extension of the conventional form of risk analysis. In any case, among risk experts, the significance of ethical and social factors is uncontested, especially as regards activities which can have far-reaching repurcussions. Some objective difficulties interfere with this goal, however: - No generally acknowledged set of ethical values exists. - Cultural influences and personal motives can interfere. - Normally a risk assessment is carried out in reference to individual facilities and within a small, clearly defined framework. Under certain circumstances, generalizations which are made for complete technological systems can lead to completely different conclusions. One contribution deals with integral views of the risks of atomic energy from an ethical and social perspective. (orig.) [de

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

    International Nuclear Information System (INIS)

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

    2007-01-01

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

  11. Moss Biomonitoring as a Tool for Radiological Exposure Assessment

    International Nuclear Information System (INIS)

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

    2013-01-01

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

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

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  13. 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

  14. 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.)

  15. 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.)

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

    Science.gov (United States)

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

    2018-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2002-02-01

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

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

    International Nuclear Information System (INIS)

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

    2002-01-01

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

  19. Radiological risks due to intrusion into a deep bedrock repository

    International Nuclear Information System (INIS)

    Nordlinder, S.; Bergstroem, U.; Edlund, O.

    1999-01-01

    The Swedish concept for disposal of high-level waste is a deep (500 m) bedrock repository (SFL) protected by multiple barriers that isolate the waste from the environment for such a long time that the physical decay will cause a substantial reduction of the radioactivity. The aim of concentration and isolation of high-level waste is to reduce the radiation risk. Intrusion in the repository may introduce a small residual risk to individuals. A risk analysis was performed comprising dose assessment and probabilities of occurrence. Intrusions may be considered to take place either due to conscious actions or by actions without any knowledge about the repository. For conscious intrusion it may be assumed that there will be enough knowledge to manage the radiation situation in a professional manner. Several reasons for making inadvertent intrusion are possible. Independently of the purpose, the most probable initial way of coming into contact with the radioactive material is by deep drilling. Examples of causes for drilling could be general scientific purposes or exploitation of geothermal energy. Dose assessments were made for intrusion due to inclined drilling directly into a canister, and drilling near an initially malfunctioning canister from which radionuclides have leaked into the groundwater. For the former case, external pathways were considered due to exposure from a core of the canister with fuel and contaminated bore dust. The most common drilling method is with water flushing for removal of bore dust, which will not cause any substantial transfer of radionuclides to air. For the second case, it was assumed that there was a well in the vicinity. The only pathway considered was therefore consumption of water because it dominates the exposure. The highest dose rates to man were, as expected, obtained by drilling into the canister. Dose rates decrease with time after closure. During the first time the relatively short-lived radionuclides Cs-137 and Sr-90 give

  20. Risk assessment and risk evaluation

    International Nuclear Information System (INIS)

    Niehaus, F.

    1978-01-01

    With the help of results of investigations and model calculations the risk of nuclear energy in routine operation is shown. In this context it is pointed out that the excellent operation results of reactors all over the world have led to the acceptability of risks from local loads no longer being in question. The attention of radiation protection is therefore focused on the emissions of long-living isotopes which collect in the atmosphere. With LWRs the risk of accidents is so minimal that statistical data is, and never will be available. One has to therefore fall back upon the so-called fault tree analyses. On the subject of risk evalution the author referred to a poll in Austria. From the result of this investigation one might conclude that nuclear energy serves as a crystallization point for a discussion of varying concepts for future development. More attention should be paid to this aspect from both sides, in order to objectify the further expansion of this source of energy. (orig./HP) [de

  1. Assessment of the radiological quality of tap waters 2008-2009

    International Nuclear Information System (INIS)

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

    2011-06-01

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

  2. Hazard waste risk assessment

    International Nuclear Information System (INIS)

    Hawley, K.A.; Napier, B.A.

    1986-01-01

    Pacific Northwest Laboratory continued to provide technical assistance to the Department of Energy (DOE) Office of Operational Safety (OOS) in the area of risk assessment for hazardous and radioactive-mixed waste management. The overall objective is to provide technical assistance to OOS in developing cost-effective risk assessment tools and strategies for bringing DOE facilities into compliance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA or Superfund) and the Resource Conservation and Recovery Act (RCRA). Major efforts during FY 1985 included (1) completing the modification of the Environmental Protection Agency (EPA) Hazard Ranking System (HRS) and developing training manuals and courses to assist in field office implementation of the modified Hazard Ranking System (mHRS); (2) initiating the development of a system for reviewing field office HRS/mHRS evaluations for appropriate use of data and appropriate application of the methodology; (3) initiating the development of a data base management system to maintain all field office HRS/mHRS scoring sheets and to support the master OOS environmental data base system; (4) developing implementation guidance for Phase I of the DOE CERCLA Program, Installation Assessment; (5) continuing to develop an objective, scientifically based methodology for DOE management to use in establishing priorities for conducting site assessments under Phase II of the DOE CERCLA Program, Confirmation; and (6) participating in developing the DOE response to EPA on the proposed listing of three sites on the National Priorities List

  3. Virtual Raters for Reproducible and Objective Assessments in Radiology

    Science.gov (United States)

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

    2016-04-01

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

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

    International Nuclear Information System (INIS)

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

    1999-01-01

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

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

    International Nuclear Information System (INIS)

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

    2007-01-01

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

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

    International Nuclear Information System (INIS)

    2011-01-01

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

  7. Risk assessment handbook

    International Nuclear Information System (INIS)

    Farmer, F.G.; Jones, J.L.; Hunt, R.N.; Roush, M.L.; Wierman, T.E.

    1990-09-01

    The Probabilistic Risk Assessment Unit at EG ampersand G Idaho has developed this handbook to provide guidance to a facility manager exploring the potential benefit to be gained by performance of a risk assessment properly scoped to meet local needs. This document is designed to help the manager control the resources expended commensurate with the risks being managed and to assure that the products can be used programmatically to support future needs in order to derive maximum beneflt from the resources expended. We present a logical and functional mapping scheme between several discrete phases of project definition to ensure that a potential customer, working with an analyst, is able to define the areas of interest and that appropriate methods are employed in the analysis. In addition the handbook is written to provide a high-level perspective for the analyst. Previously, the needed information was either scattered or existed only in the minds of experienced analysts. By compiling this information and exploring the breadth of knowledge which exists within the members of the PRA Unit, the functional relationships between the customers' needs and the product have been established

  8. 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)

  9. Concerns in assessing radiological releases to a major estuary

    International Nuclear Information System (INIS)

    Foldesi, Leslie P.

    1989-01-01

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

  10. Concerns in assessing radiological releases to a major estuary

    Energy Technology Data Exchange (ETDEWEB)

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

    1989-09-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-05-01

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

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

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  13. 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

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

    International Nuclear Information System (INIS)

    Gauron, C.

    2009-01-01

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

  15. 2007 TOXICOLOGY AND RISK ASSESSMENT ...

    Science.gov (United States)

    EPA has announced The 2007 Toxicology and Risk Assessment Conference Cincinnati Marriott North, West Chester (Cincinnati), OHApril 23- 26, 2007 - Click to register!The Annual Toxicology and Risk Assessment Conference is a unique meeting where several Government Agencies come together to discuss toxicology and risk assessment issues that are not only of concern to the government, but also to a broader audience including academia and industry. The theme of this year's conference is Emerging Issues and Challenges in Risk Assessment and the preliminary agenda includes: Plenary Sessions and prominent speakers (tentative) include: Issues of Emerging Chemical ContaminantsUncertainty and Variability in Risk Assessment Use of Mechanistic data in IARC evaluationsParallel Sessions:Uncertainty and Variability in Dose-Response Assessment Recent Advances in Toxicity and Risk Assessment of RDX The Use of Epidemiologic Data for Risk Assessment Applications Cumulative Health Risk Assessment:

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

    International Nuclear Information System (INIS)

    2011-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-05-01

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

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

    International Nuclear Information System (INIS)

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

    1995-05-01

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

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

    International Nuclear Information System (INIS)

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

    2002-01-01

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

  20. 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

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

    Science.gov (United States)

    Rosenkrantz, Andrew B; Ginocchio, Luke A

    2016-07-01

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

  2. Surgery Risk Assessment (SRA) Database

    Data.gov (United States)

    Department of Veterans Affairs — The Surgery Risk Assessment (SRA) database is part of the VA Surgical Quality Improvement Program (VASQIP). This database contains assessments of selected surgical...

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

    International Nuclear Information System (INIS)

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

    1994-03-01

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

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

    International Nuclear Information System (INIS)

    Van Nuffelen, D.

    1996-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-12-15

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

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

    International Nuclear Information System (INIS)

    Moon, Eun Kyeong; Lee, Won Jin

    2016-01-01

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

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

    Science.gov (United States)

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

    2015-09-01

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

  8. Assessment of technical risks

    Energy Technology Data Exchange (ETDEWEB)

    Jaeger, T A [Bundesanstalt fuer Materialpruefung, Berlin (Germany, F.R.)

    1978-01-01

    The safety of technical systems is so difficult to assess because the concept 'risk' contains technical-scientific factors as well as components of individual and social psychology. Immediate or short-term hazards of human life as i.e. caused by the operation of industrial plants and mediate and thus long-term hazards have to be distinguished. Characteristic for the second hazard groups is the great time-lag before the effect takes place. Thus a causal relationship can be recognized only late and not definitely. Even when the causes have been obviated the effects still show. The development of a systems-analytical model as a basis of decisive processes for the introduction of highly endangered large-scale technologies seems particularly difficult. A starting point for the quantification of the risk can still be seen in the product of the probability of realization and the extent of the damage. Public opinion, however, does not base its evaluations on an objective concept of risk but tends to have an attitude of aversion against great and disastrous accidents. On the other hand, plenty of slight accidents are accepted much more easily, even when the amount of deadly victims from accidents reaches dimensions beyond those of the rare large-scale accidents. Here, mostly the damage possible but not the probability of its occurence is seen, let alone the general use of the new technology. The value of the mathematical models for estimating risks is mainly due to the fact that they are able to clear up decisions.

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

    International Nuclear Information System (INIS)

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

    2008-01-01

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

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

    International Nuclear Information System (INIS)

    Jannik, G.T.

    1997-04-01

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

  11. Risk assessment and risk management of mycotoxins.

    Science.gov (United States)

    2012-01-01

    Risk assessment is the process of quantifying the magnitude and exposure, or probability, of a harmful effect to individuals or populations from certain agents or activities. Here, we summarize the four steps of risk assessment: hazard identification, dose-response assessment, exposure assessment, and risk characterization. Risk assessments using these principles have been conducted on the major mycotoxins (aflatoxins, fumonisins, ochratoxin A, deoxynivalenol, and zearalenone) by various regulatory agencies for the purpose of setting food safety guidelines. We critically evaluate the impact of these risk assessment parameters on the estimated global burden of the associated diseases as well as the impact of regulatory measures on food supply and international trade. Apart from the well-established risk posed by aflatoxins, many uncertainties still exist about risk assessments for the other major mycotoxins, often reflecting a lack of epidemiological data. Differences exist in the risk management strategies and in the ways different governments impose regulations and technologies to reduce levels of mycotoxins in the food-chain. Regulatory measures have very little impact on remote rural and subsistence farming communities in developing countries, in contrast to developed countries, where regulations are strictly enforced to reduce and/or remove mycotoxin contamination. However, in the absence of the relevant technologies or the necessary infrastructure, we highlight simple intervention practices to reduce mycotoxin contamination in the field and/or prevent mycotoxin formation during storage.

  12. Radiological social risk perception: something more than experts/ public discrepancies

    International Nuclear Information System (INIS)

    Prades Lopez, Ana; Gonzalez Reyes, Felisa

    1998-01-01

    One of the most important concerns of the postindustrial societies lies on the specification and quantification of risk, the Risk Assesment. However, the efforts and resources devoted to such goal have not avoided a growing worry about both the environmental conditions and the situations that potentially threaten it, generating an intense social debate about risks. In this framework, discrepancies between experts and public evaluations risks leaded to the study of social Risk perception. Several theoretical scopes have tried to characterize the phenomenon. A worthy conclusion of the empirical studies carried out on this issue is that all of them, experts and public, are influence by some factors which, in turns, affect their risk perception,. Specially striking is the fact that perception of risk among experts is also modulated by qualitative, personal and social factors. Social Risk Perception, through the process of Communication and Social Participation, has been configurated as a critical tool for both risk prevention and management

  13. Caries risk assessment

    DEFF Research Database (Denmark)

    Mejàre, I; Axelsson, S; Dahlén, G

    2014-01-01

    OBJECTIVE: To assess the ability of multivariate models and single factors to correctly identify future caries development in pre-school children and schoolchildren/adolescents. STUDY DESIGN: A systematic literature search for relevant papers was conducted with pre-determined inclusion criteria...... predictors, baseline caries experience had moderate/good accuracy in pre-school children and limited accuracy in schoolchildren/adolescents. The period of highest risk for caries incidence in permanent teeth was the first few years after tooth eruption. In general, the quality of evidence was limited....... CONCLUSIONS: Multivariate models and baseline caries prevalence performed better in pre-school children than in schoolchildren/adolescents. Baseline caries prevalence was the most accurate single predictor in all age groups. The heterogeneity of populations, models, outcome criteria, measures and reporting...

  14. HTGR containment design options: an application of probabilistic risk assessment

    International Nuclear Information System (INIS)

    1977-08-01

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

  15. 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)

  16. Risk Due to Radiological Terror Attacks With Natural Radionuclides

    Science.gov (United States)

    Friedrich, Steinhäusler; Stan, Rydell; Lyudmila, Zaitseva

    2008-08-01

    The naturally occurring radionuclides radium (Ra-226) and polonium (Po-210) have the potential to be used for criminal acts. Analysis of international incident data contained in the Database on Nuclear Smuggling, Theft and Orphan Radiation Sources (CSTO), operated at the University of Salzburg, shows that several acts of murder and terrorism with natural radionuclides have already been carried out in Europe and Russia. Five different modes of attack (T) are possible: (1) Covert irradiation of an individual in order to deliver a high individual dose; (2) Covert irradiation of a group of persons delivering a large collective dose; (3) Contamination of food or drink; (4) Generation of radioactive aerosols or solutions; (5) Combination of Ra-226 with conventional explosives (Dirty Bomb). This paper assesses the risk (R) of such criminal acts in terms of: (a) Probability of terrorist motivation deploying a certain attack mode T; (b) Probability of success by the terrorists for the selected attack mode T; (c) Primary damage consequence (C) to the attacked target (activity, dose); (d) Secondary damage consequence (C') to the attacked target (psychological and socio-economic effects); (e) Probability that the consequences (C, C') cannot be brought under control, resulting in a failure to manage successfully the emergency situation due to logistical and/or technical deficits in implementing adequate countermeasures. Extensive computer modelling is used to determine the potential impact of such a criminal attack on directly affected victims and on the environment.

  17. Risk Due to Radiological Terror Attacks With Natural Radionuclides

    International Nuclear Information System (INIS)

    Friedrich, Steinhaeusler; Lyudmila, Zaitseva; Stan, Rydell

    2008-01-01

    The naturally occurring radionuclides radium (Ra-226) and polonium (Po-210) have the potential to be used for criminal acts. Analysis of international incident data contained in the Database on Nuclear Smuggling, Theft and Orphan Radiation Sources (CSTO), operated at the University of Salzburg, shows that several acts of murder and terrorism with natural radionuclides have already been carried out in Europe and Russia. Five different modes of attack (T) are possible: (1) Covert irradiation of an individual in order to deliver a high individual dose; (2) Covert irradiation of a group of persons delivering a large collective dose; (3) Contamination of food or drink; (4) Generation of radioactive aerosols or solutions; (5) Combination of Ra-226 with conventional explosives (Dirty Bomb).This paper assesses the risk (R) of such criminal acts in terms of: (a) Probability of terrorist motivation deploying a certain attack mode T; (b) Probability of success by the terrorists for the selected attack mode T; (c) Primary damage consequence (C) to the attacked target (activity, dose); (d) Secondary damage consequence (C') to the attacked target (psychological and socio-economic effects); (e) Probability that the consequences (C, C') cannot be brought under control, resulting in a failure to manage successfully the emergency situation due to logistical and/or technical deficits in implementing adequate countermeasures. Extensive computer modelling is used to determine the potential impact of such a criminal attack on directly affected victims and on the environment

  18. Methods of risk assessment

    International Nuclear Information System (INIS)

    Jones, D.R.

    1981-01-01

    The subject is discussed under the headings: introduction (identification, quantification of risk); some approaches to risk evaluation (use of the 'no risk' principle; the 'acceptable risk' method; risk balancing; comparison of risks, benefits and other costs); cost benefit analysis; an alternative approach (tabulation and display; description and reduction of the data table); identification of potential decision sets consistent with the constraints. Some references are made to nuclear power. (U.K.)

  19. Radiological risk from consuming fish and wildlife to Native Americans on the Hanford Site (USA)

    Energy Technology Data Exchange (ETDEWEB)

    Delistraty, Damon, E-mail: DDEL461@ecy.wa.gov [Washington State Department of Ecology, N. 4601 Monroe, Spokane, WA 99205-1295 (United States); Verst, Scott Van [Washington State Department of Health, Olympia, WA (United States); Rochette, Elizabeth A. [Washington State Department of Ecology, Richland, WA (United States)

    2010-02-15

    Historical operations at the Hanford Site (Washington State, USA) have released a wide array of non-radionuclide and radionuclide contaminants into the environment. As a result of stakeholder concerns, Native American exposure scenarios have been integrated into Hanford risk assessments. Because its contribution to radiological risk to Native Americans is culturally and geographically specific but quantitatively uncertain, a fish and wildlife ingestion pathway was examined in this study. Adult consumption rates were derived from 20 Native American scenarios (based on 12 studies) at Hanford, and tissue concentrations of key radionuclides in fish, game birds, and game mammals were compiled from the Hanford Environmental Information System (HEIS) database for a recent time interval (1995-2007) during the post-operational period. It was assumed that skeletal muscle comprised 90% of intake, while other tissues accounted for the remainder. Acknowledging data gaps, median concentrations of eight radionuclides (i.e., Co-60, Cs-137, Sr-90, Tc-99, U-234, U-238, Pu-238, and Pu-239/240) in skeletal muscle and other tissues were below 0.01 and 1 pCi/g wet wt, respectively. These radionuclide concentrations were not significantly different (Bonferroni P>0.05) on and off the Hanford Site. Despite no observed difference between onsite and offsite tissue concentrations, radiation dose and risk were calculated for the fish and wildlife ingestion pathway using onsite data. With median consumption rates and radionuclide tissue concentrations, skeletal muscle provided 42% of the dose, while other tissues (primarily bone and carcass) accounted for 58%. In terms of biota, fish ingestion was the largest contributor to dose (64%). Among radionuclides, Sr-90 was dominant, accounting for 47% of the dose. At median intake and radionuclide levels, estimated annual dose (0.36 mrem/yr) was below a dose limit of 15 mrem/yr recommended by the United States Environmental Protection Agency (USEPA

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

    African Journals Online (AJOL)

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

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

    Science.gov (United States)

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

    1976-01-01

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

  2. Risk assessments ensure safer power

    Energy Technology Data Exchange (ETDEWEB)

    1982-02-19

    A growth industry is emerging devoted to the study and comparison of the economic, social and health risks posed by large industrial installations. Electricity generation is one area coming under particularly close scrutiny. Types of risk, ways of assessing risk and the difference between experts' analyses and the public perception of risk are given. An example of improved risk assessment helping to reduce deaths and injuries in coal mining is included.

  3. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-03-15

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

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

    Science.gov (United States)

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

    2017-11-01

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

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

    Directory of Open Access Journals (Sweden)

    Omoniyi Matthew Isinkaye

    2015-01-01

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

  7. Defense Programs Transportation Risk Assessment

    International Nuclear Information System (INIS)

    Clauss, D.B.

    1994-01-01

    This paper provides an overview of the methodology used in a probabilistic transportation risk assessment conducted to assess the probabilities and consequences of inadvertent dispersal of radioactive materials arising from severe transportation accidents. The model was developed for the Defense Program Transportation Risk Assessment (DPTRA) study. The analysis incorporates several enhancements relative to previous risk assessments of hazardous materials transportation including newly-developed statistics on the frequencies and severities of tractor semitrailer accidents and detailed route characterization using the 1990 Census data

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

    International Nuclear Information System (INIS)

    Liew, S.K.; Read, D.

    1987-12-01

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

  9. Risk assessment for halogenated solvents

    International Nuclear Information System (INIS)

    Travis, C.C.

    1988-01-01

    A recent development in the cancer risk area is the advent of biologically based pharmacokinetic and pharmacodynamic models. These models allow for the incorporation of biological and mechanistic data into the risk assessment process. These advances will not only improve the risk assessment process for halogenated solvents but will stimulate and guide basic research in the biological area

  10. Risk Factor Assessment Branch (RFAB)

    Science.gov (United States)

    The Risk Factor Assessment Branch (RFAB) focuses on the development, evaluation, and dissemination of high-quality risk factor metrics, methods, tools, technologies, and resources for use across the cancer research continuum, and the assessment of cancer-related risk factors in the population.

  11. Cost-effectiveness and radiological risk associated with mass chest screening

    International Nuclear Information System (INIS)

    Stieve, F.E.

    1987-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-07-01

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

  13. 137Cs Radiological risk estimation of NSD facility at Karawang site by using RESRAD onsite application: effect of cover thickness

    Science.gov (United States)

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

    2018-02-01

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

  14. 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.

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

    OpenAIRE

    Zahra Jomehzadeh; Ali Jomehzadeh; Mohammad Bagher Tavakoli

    2016-01-01

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

  16. Radiological safety assessment of a reference INTOR facility

    International Nuclear Information System (INIS)

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

    1985-03-01

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

  17. Radiological assessment of radioactive contamination on private clothing

    International Nuclear Information System (INIS)

    Schartmann, F.; Thierfeldt, S.

    2003-01-01

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

  18. HTGR accident and risk assessment

    International Nuclear Information System (INIS)

    Silady, F.A.; Everline, C.J.; Houghton, W.J.

    1982-01-01

    This paper is a synopsis of the high-temperature gas-cooled reactor probabilistic risk assessments (PRAs) performed by General Atomic Company. Principal topics presented include: HTGR safety assessments, peer interfaces, safety research, process gas explosions, quantitative safety goals, licensing applications of PRA, enhanced safety, investment risk assessments, and PRA design integration

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

    International Nuclear Information System (INIS)

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

    2012-01-01

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

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

    International Nuclear Information System (INIS)

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

    2003-01-01

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

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

    Science.gov (United States)

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

    2015-01-01

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

  2. Radiological health risks from accidents during transportation of spent nuclear fuels

    International Nuclear Information System (INIS)

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

    1988-01-01

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

  3. Information needs for risk assessment

    Energy Technology Data Exchange (ETDEWEB)

    DeRosa, C.T.; Choudhury, H.; Schoeny, R.S.

    1990-12-31

    Risk assessment can be thought of as a conceptual approach to bridge the gap between the available data and the ultimate goal of characterizing the risk or hazard associated with a particular environmental problem. To lend consistency to and to promote quality in the process, the US Environmental Protection Agency (EPA) published Guidelines for Risk Assessment of Carcinogenicity, Developmental Toxicity, Germ Cell Mutagenicity and Exposure Assessment, and Risk Assessment of Chemical Mixtures. The guidelines provide a framework for organizing the information, evaluating data, and for carrying out the risk assessment in a scientifically plausible manner. In the absence of sufficient scientific information or when abundant data are available, the guidelines provide alternative methodologies that can be employed in the risk assessment. 4 refs., 3 figs., 2 tabs.

  4. Risks arising during manipulation with radiologically specific products of biotechnical production

    International Nuclear Information System (INIS)

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

    1998-01-01

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

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

    International Nuclear Information System (INIS)

    Krishnamony, S.; Gopinath, D.V.

    1996-01-01

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

  6. Exploration Health Risks: Probabilistic Risk Assessment

    Science.gov (United States)

    Rhatigan, Jennifer; Charles, John; Hayes, Judith; Wren, Kiley

    2006-01-01

    Maintenance of human health on long-duration exploration missions is a primary challenge to mission designers. Indeed, human health risks are currently the largest risk contributors to the risks of evacuation or loss of the crew on long-duration International Space Station missions. We describe a quantitative assessment of the relative probabilities of occurrence of the individual risks to human safety and efficiency during space flight to augment qualitative assessments used in this field to date. Quantitative probabilistic risk assessments will allow program managers to focus resources on those human health risks most likely to occur with undesirable consequences. Truly quantitative assessments are common, even expected, in the engineering and actuarial spheres, but that capability is just emerging in some arenas of life sciences research, such as identifying and minimize the hazards to astronauts during future space exploration missions. Our expectation is that these results can be used to inform NASA mission design trade studies in the near future with the objective of preventing the higher among the human health risks. We identify and discuss statistical techniques to provide this risk quantification based on relevant sets of astronaut biomedical data from short and long duration space flights as well as relevant analog populations. We outline critical assumptions made in the calculations and discuss the rationale for these. Our efforts to date have focussed on quantifying the probabilities of medical risks that are qualitatively perceived as relatively high risks of radiation sickness, cardiac dysrhythmias, medically significant renal stone formation due to increased calcium mobilization, decompression sickness as a result of EVA (extravehicular activity), and bone fracture due to loss of bone mineral density. We present these quantitative probabilities in order-of-magnitude comparison format so that relative risk can be gauged. We address the effects of

  7. Analysis of radiological risks in biological research centers english

    International Nuclear Information System (INIS)

    Usera, F.; Hidalgo, R.M.; Macias, M.T.

    1998-01-01

    The work identifies the amount by which pollution and irradiation risks affect the staff. This was done in order to prevent them and also to establish the most adequate means and methodology for their reduction. For that, we have given priority to determine whether the staff applies in a correct way specific protection means available. And also, if they know the risks to which they are exposed taking into account methods they employ

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

    International Nuclear Information System (INIS)

    Williams, G.A.

    1990-01-01

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

  9. Evaluation of Van Lake (Turkey) about radiological and hydrogeological risk

    International Nuclear Information System (INIS)

    Akyil, S.; Aytas, S.; Yusan, S.; Aslani, M. A. A.; Aycan, H. A.; Eral, M.; Tuerkoezue, D. A.; Isik, M. A.; Oelgen, M. K.

    2009-01-01

    Basins which are grow in the continent and not discharge to open sea are named as a close basin. Lead, uranium and thorium are high levels in respect to open basins. Lake of Van is a close basin. In the lake basins, rivers which are discharge basin are the most important source of the heavy metal concentration. In this study, surface water, coast and deep sediments of Van Lake and Inci Kefal (fish) were analyzed as a radiological and evaluated in terms of hydrogeological. Data was obtained for natural radioactivity concentration of this lake and evaluated using geostatistical methods in a geographical information system environment and fitted for isoradioactivity contour maps. The concentration and distribution of natural radionuclides in Van Lake were investigated with the aim of evaluating the environmental radioactivity. Sixty three coastal and deep sediments, 228 lake surface waters and 12 fish samples were taken in Van Lake over the time period 2005-2008 and the distribution pattern of the measured radionuclides was presented. The mean concentrations of gross alpha and beta, eU, eTh and K-40 activities in sediments were 207±96, 1046±60, 207±96, 70±29 and 399±231 Bq/kg, respectively. On the other hand, water samples from Van Lake had mean concentrations of 0.74±0.46 Bq/L for gross alpha activity concentration, 0.02±0.01 Bq/L for gross beta activity concentration, 0.06±0.04 Bq/L for gross radium isotopes, respectively. The mean gross alpha and beta, eU, eTh and K-40 activities in fish samples were 47±18, 470±12, 0.57±0.22, 0.022±0.006, 319±11 Bq/kg, respectively. An average annual effective dose equivalent (mSv/y) was calculated.

  10. [Forensic assessment of violence risk].

    Science.gov (United States)

    Pujol Robinat, Amadeo; Mohíno Justes, Susana; Gómez-Durán, Esperanza L

    2014-03-01

    Over the last 20 years there have been steps forward in the field of scientific research on prediction and handling different violent behaviors. In this work we go over the classic concept of "criminal dangerousness" and the more current of "violence risk assessment". We analyze the evolution of such assessment from the practice of non-structured clinical expert opinion to current actuarial methods and structured clinical expert opinion. Next we approach the problem of assessing physical violence risk analyzing the HCR-20 (Assessing Risk for Violence) and we also review the classic and complex subject of the relation between mental disease and violence. One of the most problematic types of violence, difficult to assess and predict, is sexual violence. We study the different actuarial and sexual violence risk prediction instruments and in the end we advise an integral approach to the problem. We also go through partner violence risk assessment, describing the most frequently used scales, especially SARA (Spouse Assault Risk Assessment) and EPV-R. Finally we give practical advice on risk assessment, emphasizing the importance of having maximum information about the case, carrying out a clinical examination, psychopathologic exploration and the application of one of the described risk assessment scales. We'll have to express an opinion about the dangerousness/risk of future violence from the subject and some recommendations on the conduct to follow and the most advisable treatment. Copyright © 2014 Elsevier España, S.L. All rights reserved.

  11. Risk assessment and regulation

    International Nuclear Information System (INIS)

    1981-01-01

    The approach to determining how safe is safe for the nuclear industry is to ensure that the risks are comparable with or less than those of other safe industries. There are some problems in implementing such an approach, because the effects of low levels of radiation are stochastic and assumptions are required in estimating the risks. A conservative approach has generally been adopted. Risk estimates across different activities are a useful indication of where society may be overspending or underspending to reduce risk, but the analysis has to take account of public preferences. Once risks have been estimated, limits may be chosen which the industry is expected to meet under normal and postulated accident conditions. Limits have been set so that nuclear risks do not exceed those in safe industries, and under normal conditions nuclear facilities operate at levels far below these specified limits

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-10-15

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

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

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  14. Models for Pesticide Risk Assessment

    Science.gov (United States)

    EPA considers the toxicity of the pesticide as well as the amount of pesticide to which a person or the environments may be exposed in risk assessment. Scientists use mathematical models to predict pesticide concentrations in exposure assessment.

  15. Using risk assessment in periodontics.

    Science.gov (United States)

    Woodman, Alan J

    2014-08-01

    Risk assessment has become a regular feature in both dental practice and society as a whole, and principles used to assess risk in society are similar to those used in a clinical setting. Although the concept of risk assessment as a prognostic indicator for periodontal disease incidence and activity is well established in the management of periodontitis, the use of risk assessment to manage the practical treatment of periodontitis and its sequelae appears to have less foundation. A simple system of initial risk assessment - building on the use of the Basic Periodontal Examination (BPE), clinical, medical and social factors - is described, linked to protocols for delivering care suited to general dental practice and stressing the role of long-term supportive care. The risks of not treating the patient are considered, together with the possible causes of failure, and the problems of successful treatment are illustrated by the practical management of post-treatment recession.

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

    Energy Technology Data Exchange (ETDEWEB)

    FRMAC Health and Safety Working Group

    2012-03-20

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

  17. Radiological protection, environmental implications, health and risk management: forum

    International Nuclear Information System (INIS)

    2008-01-01

    Topics related to the radioactivity or radiation are presented. The importance of protection and security measures that are required both for public health, occupational health and the medical radiation is analyzed. In addition, it emphasizes the risks faced by professionals who work with radioactivity. Issues that confront the serious environmental implications of such activities are also showed [es

  18. Environmental Risk Communication through Qualitative Risk Assessment

    Directory of Open Access Journals (Sweden)

    Sabre J. Coleman

    2014-06-01

    Full Text Available Environmental analysts are often hampered in communicating the risks of environmental contaminants due to the myriad of regulatory requirements that are applicable. The use of a qualitative, risk-based control banding strategy for assessment and control of potential environmental contaminants provides a standardized approach to improve risk communication. Presented is a model that provides an effective means for determining standardized responses and controls for common environmental issues based on the level of risk. The model is designed for integration within an occupational health and safety management system to provide a multidisciplinary environmental and occupational risk management approach. This environmental model, which utilizes multidisciplinary control banding strategies for delineating risk, complements the existing Risk Level Based Management System, a proven method in a highly regulated facility for occupational health and safety. A simplified environmental risk matrix is presented that is stratified over four risk levels. Examples of qualitative environmental control banding strategies are presented as they apply to United States regulations for construction, research activities, facility maintenance, and spill remediation that affect air, water, soil, and waste disposal. This approach offers a standardized risk communication language for multidisciplinary issues that will improve communications within and between environmental health and safety professionals, workers, and management.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-04-01

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

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

    International Nuclear Information System (INIS)

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

    1992-01-01

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

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

    International Nuclear Information System (INIS)

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

    1994-04-01

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

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

    International Nuclear Information System (INIS)

    1986-06-01

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

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

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  4. RESIDUAL RISK ASSESSMENT: ETHYLENE OXIDE ...

    Science.gov (United States)

    This document describes the residual risk assessment for the Ethylene Oxide Commercial Sterilization source category. For stationary sources, section 112 (f) of the Clean Air Act requires EPA to assess risks to human health and the environment following implementation of technology-based control standards. If these technology-based control standards do not provide an ample margin of safety, then EPA is required to promulgate addtional standards. This document describes the methodology and results of the residual risk assessment performed for the Ethylene Oxide Commercial Sterilization source category. The results of this analyiss will assist EPA in determining whether a residual risk rule for this source category is appropriate.

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

    International Nuclear Information System (INIS)

    Lecomte, J.F.; Schieber, C.

    2000-01-01

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

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

    International Nuclear Information System (INIS)

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

    1995-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-05-15

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

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

    International Nuclear Information System (INIS)

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

    1995-01-01

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

  9. 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

  10. 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.

  11. Comments by a peer review panel on the computerized radiological risk investigation system (CRRIS)

    International Nuclear Information System (INIS)

    Baker, D.A.

    1988-08-01

    This document represents the comprehensive review by experts of the documents describing the models, computer programs, and data bases making up the Computerized Radiological Risk Investigation System (CRRIS). The CRRIS methodology has been produced for the US Environmental Protection Agency's (EPA) Office of Radiation Programs (ORP) by the Health and Safety Research Division of Oak Ridge National Laboratory (ORNL) to assess the significance of releases of radioactive material from facilities handling such materials. The comments covered a wide range of aspects of the CRRIS models. Special review topics covered were uncertainty, validation, verification, and health effects. The reports making up the CRRIS documentation were reviewed in detail. The following are some of the more frequent comments about the methodology. This is a very comprehensive work, but too complex and hard to use. Too little explanation of some of the assumptions taken such as variance from standard ICRP organ weighting factors. Overly complex model for soil to root transfer and interception fraction. Gaussian plume model was used, when more state-of-art models are available. 35 refs

  12. Comments by a peer review panel on the computerized radiological risk investigation system (CRRIS)

    Energy Technology Data Exchange (ETDEWEB)

    Baker, D.A. (ed.)

    1988-08-01

    This document represents the comprehensive review by experts of the documents describing the models, computer programs, and data bases making up the Computerized Radiological Risk Investigation System (CRRIS). The CRRIS methodology has been produced for the US Environmental Protection Agency's (EPA) Office of Radiation Programs (ORP) by the Health and Safety Research Division of Oak Ridge National Laboratory (ORNL) to assess the significance of releases of radioactive material from facilities handling such materials. The comments covered a wide range of aspects of the CRRIS models. Special review topics covered were uncertainty, validation, verification, and health effects. The reports making up the CRRIS documentation were reviewed in detail. The following are some of the more frequent comments about the methodology. This is a very comprehensive work, but too complex and hard to use. Too little explanation of some of the assumptions taken such as variance from standard ICRP organ weighting factors. Overly complex model for soil to root transfer and interception fraction. Gaussian plume model was used, when more state-of-art models are available. 35 refs.

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

    International Nuclear Information System (INIS)

    Shi Dongsheng; Di Yuming; Zhou Chunlin

    2007-01-01

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

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

    International Nuclear Information System (INIS)

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

    1988-01-01

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

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

    International Nuclear Information System (INIS)

    Nass, Jens

    2010-01-01

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

  16. Radiological impact assessment of the rehabilitated Nabarlek uranium minesite

    International Nuclear Information System (INIS)

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

    1998-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2006-09-15

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

  18. Risk indices in comparative risk assessment studies

    International Nuclear Information System (INIS)

    Hubert, P.

    1984-01-01

    More than a decade ago the development of comparative risk assessment studies aroused overwhelming interest. There was no doubt that data on the health and safety aspects of energy systems would greatly benefit, or even end, the debate on nuclear energy. Although such attempts are still strongly supported, the rose-coloured expectations of the early days have faded. The high uncertainties, and the contradictory aspect, of the first results might explain this evolution. The loose connection between the range of computed risk indices and the questions on which the debate was focused is another reason for this decline in interest. Important research work is being carried out aiming at reducing the different kinds of uncertainties. Rather than the uncertainties, the paper considers the meaning of available risk indices and proposes more significant indices with respect to the goals of risk assessment. First, the indices which are of frequent use in comparative studies are listed. The stress is put on a French comparative study from which most examples are drawn. Secondly, the increase in magnitude of the indices and the decrease in the attributability of the risk to a given system is shown to be a consequence of the trend towards more comprehensive analyses. Thirdly, the ambiguity of such indices as the collective occupational risk is underlined, and a possible solution is suggested. Whenever risk assessments are related to pragmatic decision making problems it is possible to find satisfactory risk indices. The development of cost-effectiveness analyses and the proposals for quantitative safety goals clearly demonstrate this point. In the field of comparison of social impacts some proposals are made, but there remain some gaps still to be filled. (author)

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

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  20. 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.

  1. 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

  2. Status report on the EPRI fuel cycle accident risk assessment

    International Nuclear Information System (INIS)

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

    1979-07-01

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

  3. Implications of probabilistic risk assessment

    International Nuclear Information System (INIS)

    Cullingford, M.C.; Shah, S.M.; Gittus, J.H.

    1987-01-01

    Probabilistic risk assessment (PRA) is an analytical process that quantifies the likelihoods, consequences and associated uncertainties of the potential outcomes of postulated events. Starting with planned or normal operation, probabilistic risk assessment covers a wide range of potential accidents and considers the whole plant and the interactions of systems and human actions. Probabilistic risk assessment can be applied in safety decisions in design, licensing and operation of industrial facilities, particularly nuclear power plants. The proceedings include a review of PRA procedures, methods and technical issues in treating uncertainties, operating and licensing issues and future trends. Risk assessment for specific reactor types or components and specific risks (eg aircraft crashing onto a reactor) are used to illustrate the points raised. All 52 articles are indexed separately. (U.K.)

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

    International Nuclear Information System (INIS)

    Lefaure, C.

    1995-01-01

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

  5. Research progress of non-human species radiological impact and assessment

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  6. Tools for Microbiological risk assessment

    DEFF Research Database (Denmark)

    Bassett, john; Nauta, Maarten; Lindqvist, Roland

    can increase the understanding of microbiological risks in foods. It is timely to inform food safety professionals about the availability and utility of MRA tools. Therefore, the focus of this report is to aid the food safety manager by providing a concise summary of the tools available for the MRA......Microbiological Risk Assessment (MRA) has emerged as a comprehensive and systematic approach for addressing the risk of pathogens in specific foods and/or processes. At government level, MRA is increasingly recognised as a structured and objective approach to understand the level of risk in a given...... food/pathogen scenario. Tools developed so far support qualitative and quantitative assessments of the risk that a food pathogen poses to a particular population. Risk can be expressed as absolute numbers or as relative (ranked) risks. The food industry is beginning to appreciate that the tools for MRA...

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

    International Nuclear Information System (INIS)

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

    2013-01-01

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

  8. Integrated climate change risk assessment:

    DEFF Research Database (Denmark)

    Kaspersen, Per Skougaard; Halsnæs, Kirsten

    2017-01-01

    Risk assessments of flooding in urban areas during extreme precipitation for use in, for example, decision-making regarding climate adaptation, are surrounded by great uncertainties stemming from climate model projections, methods of downscaling and the assumptions of socioeconomic impact models...... to address the complex linkages between the different kinds of data required in assessing climate adaptation. It emphasizes that the availability of spatially explicit data can reduce the overall uncertainty of the risk assessment and assist in identifying key vulnerable assets. The usefulness...... of such a framework is demonstrated by means of a risk assessment of flooding from extreme precipitation for the city of Odense, Denmark. A sensitivity analysis shows how the presence of particularly important assets, such as cultural and historical heritage, may be addressed in assessing such risks. The output...

  9. Commercial low-level radioactive waste transportation liability and radiological risk

    Energy Technology Data Exchange (ETDEWEB)

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

    1992-08-01

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

  10. Commercial low-level radioactive waste transportation liability and radiological risk

    International Nuclear Information System (INIS)

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

    1992-08-01

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

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

    International Nuclear Information System (INIS)

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

    2006-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2006-07-01

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

  13. Carcinogen risk assessment

    International Nuclear Information System (INIS)

    Hazelwoold, R.N.

    1987-01-01

    This article describes the methods by which risk factors for carcinogenic hazards are determined and the limitations inherent in the process. From statistical and epidemiological studies, the major identifiable factors related to cancer in the United States were determined to be cigarette smoking, diet, reproductive and sexual behavior, infections, ultraviolet and ionizing radiation, and alcohol consumption. The incidence of lung cancer due to air pollutants was estimated to be less than 2%. Research needs were discussed

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

    International Nuclear Information System (INIS)

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

    2005-01-01

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

  15. Assessment of the radiological impact of the transport of radioactive materials

    International Nuclear Information System (INIS)

    1986-12-01

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

  16. Probabilistic risk assessment methodology

    International Nuclear Information System (INIS)

    Shinaishin, M.A.

    1988-06-01

    The objective of this work is to provide the tools necessary for clear identification of: the purpose of a Probabilistic Risk Study, the bounds and depth of the study, the proper modeling techniques to be used, the failure modes contributing to the analysis, the classical and baysian approaches for manipulating data necessary for quantification, ways for treating uncertainties, and available computer codes that may be used in performing such probabilistic analysis. In addition, it provides the means for measuring the importance of a safety feature to maintaining a level of risk at a Nuclear Power Plant and the worth of optimizing a safety system in risk reduction. In applying these techniques so that they accommodate our national resources and needs it was felt that emphasis should be put on the system reliability analysis level of PRA. Objectives of such studies could include: comparing systems' designs of the various vendors in the bedding stage, and performing grid reliability and human performance analysis using national specific data. (author)

  17. Probabilistic risk assessment methodology

    Energy Technology Data Exchange (ETDEWEB)

    Shinaishin, M A

    1988-06-15

    The objective of this work is to provide the tools necessary for clear identification of: the purpose of a Probabilistic Risk Study, the bounds and depth of the study, the proper modeling techniques to be used, the failure modes contributing to the analysis, the classical and baysian approaches for manipulating data necessary for quantification, ways for treating uncertainties, and available computer codes that may be used in performing such probabilistic analysis. In addition, it provides the means for measuring the importance of a safety feature to maintaining a level of risk at a Nuclear Power Plant and the worth of optimizing a safety system in risk reduction. In applying these techniques so that they accommodate our national resources and needs it was felt that emphasis should be put on the system reliability analysis level of PRA. Objectives of such studies could include: comparing systems' designs of the various vendors in the bedding stage, and performing grid reliability and human performance analysis using national specific data. (author)

  18. Probabilistic risk assessment, Volume I

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

    This book contains 158 papers presented at the International Topical Meeting on Probabilistic Risk Assessment held by the American Nuclear Society (ANS) and the European Nuclear Society (ENS) in Port Chester, New York in 1981. The meeting was second in a series of three. The main focus of the meeting was on the safety of light water reactors. The papers discuss safety goals and risk assessment. Quantitative safety goals, risk assessment in non-nuclear technologies, and operational experience and data base are also covered. Included is an address by Dr. Chauncey Starr

  19. Risk assessment in maritime transportation

    International Nuclear Information System (INIS)

    Soares, C. Guedes; Teixeira, A.P.

    2001-01-01

    A review is presented of different approaches to quantify the risk in maritime transportation. The discussion of several accident statistics provides a global assessment of the risk levels and its differentiation in ship types and main types of ship losses. Early studies in the probability of ship loss by foundering and capsizing are reviewed. The approaches used to assess the risk of structural design are addressed. Finally a brief account is given of recent development of using formal safety assessments to support decision making on legislation applicable internationally to maritime transportation

  20. Framework for ecological risk assessment

    International Nuclear Information System (INIS)

    Rodier, D.; Norton, S.

    1992-02-01

    Increased interest in ecological issues such as global climate change, habitat loss, acid deposition, reduced biological diversity, and the ecological impacts of pesticides and toxic chemicals prompts this U.S. Environmental Protection Agency (EPA) report, A Framework for Ecological Risk Assessment ('Framework Report'). The report describes basic elements, or a framework, for evaluating scientific information on the adverse effects of physical and chemical stressors on the environment. The framework offers starting principles and a simple structure as guidance for current ecological risk assessments and as a foundation for future EPA proposals for risk assessment guidelines

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

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  2. CEA: assessment of risk management 2011

    International Nuclear Information System (INIS)

    2012-06-01

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

  3. Risk Assessment and Integration Team (RAIT) Portfolio Risk Analysis Strategy

    Science.gov (United States)

    Edwards, Michelle

    2010-01-01

    Impact at management level: Qualitative assessment of risk criticality in conjunction with risk consequence, likelihood, and severity enable development of an "investment policy" towards managing a portfolio of risks. Impact at research level: Quantitative risk assessments enable researchers to develop risk mitigation strategies with meaningful risk reduction results. Quantitative assessment approach provides useful risk mitigation information.

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

    Science.gov (United States)

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

    1997-07-01

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

  5. Quantitative risk assessment system (QRAS)

    Science.gov (United States)

    Weinstock, Robert M (Inventor); Smidts, Carol S (Inventor); Mosleh, Ali (Inventor); Chang, Yung-Hsien (Inventor); Swaminathan, Sankaran (Inventor); Groen, Francisco J (Inventor); Tan, Zhibin (Inventor)

    2001-01-01

    A quantitative risk assessment system (QRAS) builds a risk model of a system for which risk of failure is being assessed, then analyzes the risk of the system corresponding to the risk model. The QRAS performs sensitivity analysis of the risk model by altering fundamental components and quantifications built into the risk model, then re-analyzes the risk of the system using the modifications. More particularly, the risk model is built by building a hierarchy, creating a mission timeline, quantifying failure modes, and building/editing event sequence diagrams. Multiplicities, dependencies, and redundancies of the system are included in the risk model. For analysis runs, a fixed baseline is first constructed and stored. This baseline contains the lowest level scenarios, preserved in event tree structure. The analysis runs, at any level of the hierarchy and below, access this baseline for risk quantitative computation as well as ranking of particular risks. A standalone Tool Box capability exists, allowing the user to store application programs within QRAS.

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

    International Nuclear Information System (INIS)

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

    1993-01-01

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

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

    International Nuclear Information System (INIS)

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

    1993-01-01

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

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

    International Nuclear Information System (INIS)

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

    2014-04-01

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

  9. Risk assessment: An employer's perspective

    International Nuclear Information System (INIS)

    Williams, K.C.

    1992-01-01

    There is no question that a careful assessment of risk is essential for safe industrial operations. For that reason, a thoughtful analysis of the effectiveness of available risk assessment technologies is prerequisite for responsible corporate decision making. An 'employer's' perspective on risk assessment cannot be constrained by any artificial restrictions which that term may imply. In reality, all those who are involved in the execution of an industrial enterprise: managers, regulators, the affected public, and especially those employees exposed to hazards, are necessarily partners in assessment of risk. The perspective of this paper is that of the oil and gas industry, in which the author's organization, Exxon Company, International, participates. The paper addresses what Exxon requires to assess and manage risk in its worldwide operations. The author is aware, however, through contacts with industry colleagues, that some of Exxon's initiatives are representative of similar actions being taken by others. 1992 is the European Year of Safety, Health and Hygiene, coinciding with the United Kingdom's Presidency of the European Council. It is also the year in which new 'goal-setting' regulations covering safety in the U.K. offshore oil industry were put forward by the Health and Safety Commission. These regulations, based largely on Lord Cullen's recommendations following the Piper Alpha tragedy, set the pace for safety in the British North Sea and will significantly impact the safety of offshore oil installations worldwide. The requirement for risk assessment, using a systematic process of analysing and evaluating risk, is a key component of this safety regime

  10. Risk assessment: An employer's perspective

    Energy Technology Data Exchange (ETDEWEB)

    Williams, K C [Exxon International (United States)

    1992-07-01

    There is no question that a careful assessment of risk is essential for safe industrial operations. For that reason, a thoughtful analysis of the effectiveness of available risk assessment technologies is prerequisite for responsible corporate decision making. An 'employer's' perspective on risk assessment cannot be constrained by any artificial restrictions which that term may imply. In reality, all those who are involved in the execution of an industrial enterprise: managers, regulators, the affected public, and especially those employees exposed to hazards, are necessarily partners in assessment of risk. The perspective of this paper is that of the oil and gas industry, in which the author's organization, Exxon Company, International, participates. The paper addresses what Exxon requires to assess and manage risk in its worldwide operations. The author is aware, however, through contacts with industry colleagues, that some of Exxon's initiatives are representative of similar actions being taken by others. 1992 is the European Year of Safety, Health and Hygiene, coinciding with the United Kingdom's Presidency of the European Council. It is also the year in which new 'goal-setting' regulations covering safety in the U.K. offshore oil industry were put forward by the Health and Safety Commission. These regulations, based largely on Lord Cullen's recommendations following the Piper Alpha tragedy, set the pace for safety in the British North Sea and will significantly impact the safety of offshore oil installations worldwide. The requirement for risk assessment, using a systematic process of analysing and evaluating risk, is a key component of this safety regime.

  11. Building Better Environmental Risk Assessments

    Science.gov (United States)

    Layton, Raymond; Smith, Joe; Macdonald, Phil; Letchumanan, Ramatha; Keese, Paul; Lema, Martin

    2015-01-01

    Risk assessment is a reasoned, structured approach to address uncertainty based on scientific and technical evidence. It forms the foundation for regulatory decision-making, which is bound by legislative and policy requirements, as well as the need for making timely decisions using available resources. In order to be most useful, environmental risk assessments (ERAs) for genetically modified (GM) crops should provide consistent, reliable, and transparent results across all types of GM crops, traits, and environments. The assessments must also separate essential information from scientific or agronomic data of marginal relevance or value for evaluating risk and complete the assessment in a timely fashion. Challenges in conducting ERAs differ across regulatory systems – examples are presented from Canada, Malaysia, and Argentina. One challenge faced across the globe is the conduct of risk assessments with limited resources. This challenge can be overcome by clarifying risk concepts, placing greater emphasis on data critical to assess environmental risk (for example, phenotypic and plant performance data rather than molecular data), and adapting advances in risk analysis from other relevant disciplines. PMID:26301217

  12. Building Better Environmental Risk Assessments.

    Science.gov (United States)

    Layton, Raymond; Smith, Joe; Macdonald, Phil; Letchumanan, Ramatha; Keese, Paul; Lema, Martin

    2015-01-01

    Risk assessment is a reasoned, structured approach to address uncertainty based on scientific and technical evidence. It forms the foundation for regulatory decision-making, which is bound by legislative and policy requirements, as well as the need for making timely decisions using available resources. In order to be most useful, environmental risk assessments (ERAs) for genetically modified (GM) crops should provide consistent, reliable, and transparent results across all types of GM crops, traits, and environments. The assessments must also separate essential information from scientific or agronomic data of marginal relevance or value for evaluating risk and complete the assessment in a timely fashion. Challenges in conducting ERAs differ across regulatory systems - examples are presented from Canada, Malaysia, and Argentina. One challenge faced across the globe is the conduct of risk assessments with limited resources. This challenge can be overcome by clarifying risk concepts, placing greater emphasis on data critical to assess environmental risk (for example, phenotypic and plant performance data rather than molecular data), and adapting advances in risk analysis from other relevant disciplines.

  13. Building better environmental risk assessments

    Directory of Open Access Journals (Sweden)

    Raymond eLayton

    2015-08-01

    Full Text Available Risk assessment is a reasoned, structured approach to address uncertainty based on scientific and technical evidence. It forms the foundation for regulatory decision making, which is bound by legislative and policy requirements, as well as the need for making timely decisions using available resources. In order to be most useful, environmental risk assessments (ERA for genetically modified (GM crops should provide consistent, reliable, and transparent results across all types of GM crops, traits, and environments. The assessments must also separate essential information from scientific or agronomic data of marginal relevance or value for evaluating risk and complete the assessment in a timely fashion. Challenges in conducting ERAs differ across regulatory systems – examples are presented from Canada, Malaysia, and Argentina. One challenge faced across the globe is the conduct of risk assessments with limited resources. This challenge can be overcome by clarifying risk concepts, placing greater emphasis on data critical to assess environmental risk (for example, phenotypic and plant performance data rather than molecular data, and adapting advances in risk analysis from other relevant disciplines.

  14. Risk assessment in international operations

    International Nuclear Information System (INIS)

    Stricklin, Daniela L.

    2008-01-01

    During international peace-keeping missions, a diverse number of non-battle hazards may be encountered, which range from heavily polluted areas, endemic disease, toxic industrial materials, local violence, traffic, and even psychological factors. Hence, elevated risk levels from a variety of sources are encountered during deployments. With the emphasis within the Swedish military moving from national defense towards prioritization of international missions in atypical environments, the risk of health consequences, including long term health effects, has received greater consideration. The Swedish military is interested in designing an optimal approach for assessment of health threats during deployments. The Medical Intelligence group at FOI CBRN Security and Defence in Umea has, on request from and in collaboration with the Swedish Armed Forces, reviewed a variety of international health threat and risk assessment models for military operations. Application of risk assessment methods used in different phases of military operations will be reviewed. An overview of different international approaches used in operational risk management (ORM) will be presented as well as a discussion of the specific needs and constraints for health risk assessment in military operations. This work highlights the specific challenges of risk assessment that are unique to the deployment setting such as the assessment of exposures to a variety of diverse hazards concurrently

  15. Assessment and perception of risk

    Energy Technology Data Exchange (ETDEWEB)

    Daglish, J

    1981-01-01

    A recent two-day meeting was called by the Royal Society to discuss all types of risks, but symptomatic of the concerns of most of those present, the discussion centred mainly on the risks inherent in energy production and use. Among the subjects considered were public perception of differing risks, and how these are ranked, and risks versus benefits. Quotations from and summaries of many of the papers presented show that it was generally felt that scientists must be very careful in the way that they use numerical assessments of risk and that they should pay more attention than they have to social and political factors.

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

    International Nuclear Information System (INIS)

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

    2015-01-01

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

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

    Directory of Open Access Journals (Sweden)

    Zahra Jomehzadeh

    2016-03-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-09-15

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

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

    Science.gov (United States)

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

    2016-12-01

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

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

    Science.gov (United States)

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

    2017-01-01

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

  1. Clean Slate transportation and human health risk assessment

    International Nuclear Information System (INIS)

    1997-02-01

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

  2. Deterministic quantitative risk assessment development

    Energy Technology Data Exchange (ETDEWEB)

    Dawson, Jane; Colquhoun, Iain [PII Pipeline Solutions Business of GE Oil and Gas, Cramlington Northumberland (United Kingdom)

    2009-07-01

    Current risk assessment practice in pipeline integrity management is to use a semi-quantitative index-based or model based methodology. This approach has been found to be very flexible and provide useful results for identifying high risk areas and for prioritizing physical integrity assessments. However, as pipeline operators progressively adopt an operating strategy of continual risk reduction with a view to minimizing total expenditures within safety, environmental, and reliability constraints, the need for quantitative assessments of risk levels is becoming evident. Whereas reliability based quantitative risk assessments can be and are routinely carried out on a site-specific basis, they require significant amounts of quantitative data for the results to be meaningful. This need for detailed and reliable data tends to make these methods unwieldy for system-wide risk k assessment applications. This paper describes methods for estimating risk quantitatively through the calibration of semi-quantitative estimates to failure rates for peer pipeline systems. The methods involve the analysis of the failure rate distribution, and techniques for mapping the rate to the distribution of likelihoods available from currently available semi-quantitative programs. By applying point value probabilities to the failure rates, deterministic quantitative risk assessment (QRA) provides greater rigor and objectivity than can usually be achieved through the implementation of semi-quantitative risk assessment results. The method permits a fully quantitative approach or a mixture of QRA and semi-QRA to suit the operator's data availability and quality, and analysis needs. For example, consequence analysis can be quantitative or can address qualitative ranges for consequence categories. Likewise, failure likelihoods can be output as classical probabilities or as expected failure frequencies as required. (author)

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

    Science.gov (United States)

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

    2014-12-01

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

  4. Modern biogeochemistry environmental risk assessment

    CERN Document Server

    Bashkin, Vladimir N

    2006-01-01

    Most books deal mainly with various technical aspects of ERA description and calculationsAims at generalizing the modern ideas of both biogeochemical and environmental risk assessment during recent yearsAims at supplementing the existing books by providing a modern understanding of mechanisms that are responsible for the ecological risk for human beings and ecosystem

  5. Risk assessment future cash flows

    OpenAIRE

    Chachina H. G.

    2012-01-01

    This article is about risk assessment in planning future cash flows. Discount rate in DCF-model must include four factors: risk cash flow, inflation, value of investments, turnover assets. This has an influence net present value cash flow and make his incomparable.

  6. Test reactor risk assessment methodology

    International Nuclear Information System (INIS)

    Jennings, R.H.; Rawlins, J.K.; Stewart, M.E.

    1976-04-01

    A methodology has been developed for the identification of accident initiating events and the fault modeling of systems, including common mode identification, as these methods are applied in overall test reactor risk assessment. The methods are exemplified by a determination of risks to a loss of primary coolant flow in the Engineering Test Reactor

  7. Anthropic Risk Assessment on Biodiversity

    Science.gov (United States)

    Piragnolo, M.; Pirotti, F.; Vettore, A.; Salogni, G.

    2013-01-01

    This paper presents a methodology for risk assessment of anthropic activities on habitats and species. The method has been developed for Veneto Region, in order to simplify and improve the quality of EIA procedure (VINCA). Habitats and species, animals and plants, are protected by European Directive 92/43/EEC and 2009/147/EC but they are subject at hazard due to pollution produced by human activities. Biodiversity risks may conduct to deterioration and disturbance in ecological niches, with consequence of loss of biodiversity. Ecological risk assessment applied on Natura 2000 network, is needed to best practice of management and monitoring of environment and natural resources. Threats, pressure and activities, stress and indicators may be managed by geodatabase and analysed using GIS technology. The method used is the classic risk assessment in ecological context, and it defines the natural hazard as influence, element of risk as interference and vulnerability. Also it defines a new parameter called pressure. It uses risk matrix for the risk analysis on spatial and temporal scale. The methodology is qualitative and applies the precautionary principle in environmental assessment. The final product is a matrix which excludes the risk and could find application in the development of a territorial information system.

  8. Cloud computing assessing the risks

    CERN Document Server

    Carstensen, Jared; Golden, Bernard

    2012-01-01

    Cloud Computing: Assessing the risks answers these questions and many more. Using jargon-free language and relevant examples, analogies and diagrams, it is an up-to-date, clear and comprehensive guide the security, governance, risk, and compliance elements of Cloud Computing.

  9. Improving pandemic influenza risk assessment

    Science.gov (United States)

    Assessing the pandemic risk posed by specific non-human influenza A viruses remains a complex challenge. As influenza virus genome sequencing becomes cheaper, faster and more readily available, the ability to predict pandemic potential from sequence data could transform pandemic influenza risk asses...

  10. Evaluation of thermal risk assessment

    International Nuclear Information System (INIS)

    Loos, J.J.; Perry, E.S.

    1993-01-01

    Risk assessment was done in 1983 to estimate the ecological hazard of increasing the generating load and thermal output of an electric generating station. Subsequently, long-term monitoring in the vicinity of the station allowed verification of the predictions made in the risk assessment. This presentation will review the efficacy of early risk assessment methods in producing useful predictions from a resource management point of view. In 1984, the Chalk Point Generating facility of the Potomac Electric Power Company increased it's median generating load by 100%. Prior to this operational change, the Academy of Natural Sciences of Philadelphia synthesized site specific data, model predictions, and results from literature to assess the risk of additional waste heat to the Patuxent River subestuary of Chesapeake Bay. Risk was expressed as the number of days per year that various species of fish and the blue crab would be expected to avoid the discharge vicinity. Accuracy of these predictions is assessed by comparing observed fish and crab distributions and their observed frequencies of avoidance to those predicted. It is concluded that the predictions of this early risk assessment were sufficiently accurate to produce a reliable resource management decision

  11. Failure rate data for fusion safety and risk assessment

    International Nuclear Information System (INIS)

    Cadwallader, L.C.

    1993-01-01

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

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

    International Nuclear Information System (INIS)

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

    1982-05-01

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

  13. Pathology and risk assessment

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    Programs for providing basic data for use in evaluating the hazard to man from exposure to radiation and other energy-related pollutants are reviewed. A computer program was developed that takes the existing mortality and fertility data on a given population and applies dose-response coefficients and estimated increments of exposure to chemical or radioactive effluents and derives the excess deaths by age and sex for 5-year intervals. The program was used in an analysis of the health effects of airborne coal combustion effluents. Preliminary results are reported from a study of the influence of products of fossil fuel combustion on the spontaneous activity patterns and daily metabolic cycles of mice as a factor of age, environment, and genetic constitution. Preliminary results are reported from studies on the early and late effects of polycyclic hydrocarbons on the immune competence of mice. Studies to determine the risk to human populations from radionuclides released to the environment from nuclear energy facilities use relative toxicity and dose response data from laboratory animals of different body size and life span and comparisons of the effects of internal exposure with those of external exposure to fission neutrons or gamma sources

  14. Taking the Risk Out of Risk Assessment

    Science.gov (United States)

    2005-01-01

    The ability to understand risks and have the right strategies in place when risky events occur is essential in the workplace. More and more organizations are being confronted with concerns over how to measure their risks or what kind of risks they can take when certain events transpire that could have a negative impact. NASA is one organization that faces these challenges on a daily basis, as effective risk management is critical to the success of its missions especially the Space Shuttle missions. On July 29, 1996, former NASA Administrator Daniel Goldin charged NASA s Office of Safety and Mission Assurance with developing a probabilistic risk assessment (PRA) tool to support decisions on the funding of Space Shuttle upgrades. When issuing the directive, Goldin said, "Since I came to NASA [in 1992], we've spent billions of dollars on Shuttle upgrades without knowing how much they improve safety. I want a tool to help base upgrade decisions on risk." Work on the PRA tool began immediately. The resulting prototype, the Quantitative Risk Assessment System (QRAS) Version 1.0, was jointly developed by NASA s Marshall Space Flight Center, its Office of Safety and Mission Assurance, and researchers at the University of Maryland. QRAS software automatically expands the reliability logic models of systems to evaluate the probability of highly detrimental outcomes occurring in complex systems that are subject to potential accident scenarios. Even in its earliest forms, QRAS was used to begin PRA modeling of the Space Shuttle. In parallel, the development of QRAS continued, with the goal of making it a world-class tool, one that was especially suited to NASA s unique needs. From the beginning, an important conceptual goal in the development of QRAS was for it to help bridge the gap between the professional risk analyst and the design engineer. In the past, only the professional risk analyst could perform, modify, use, and perhaps even adequately understand PRA. NASA wanted

  15. Avalanche risk assessment in Russia

    Science.gov (United States)

    Komarov, Anton; Seliverstov, Yury; Sokratov, Sergey; Glazovskaya, Tatiana; Turchaniniva, Alla

    2017-04-01

    The avalanche prone area covers about 3 million square kilometers or 18% of total area of Russia and pose a significant problem in most mountain regions of the country. The constant growth of economic activity, especially in the North Caucasus region and therefore the increased avalanche hazard lead to the demand of the large-scale avalanche risk assessment methods development. Such methods are needed for the determination of appropriate avalanche protection measures as well as for economic assessments during all stages of spatial planning of the territory. The requirement of natural hazard risk assessments is determined by the Federal Law of Russian Federation. However, Russian Guidelines (SP 11-103-97; SP 47.13330.2012) are not clearly presented concerning avalanche risk assessment calculations. A great size of Russia territory, vast diversity of natural conditions and large variations in type and level of economic development of different regions cause significant variations in avalanche risk values. At the first stage of research the small scale avalanche risk assessment was performed in order to identify the most common patterns of risk situations and to calculate full social risk and individual risk. The full social avalanche risk for the territory of country was estimated at 91 victims. The area of territory with individual risk values lesser then 1×10(-6) covers more than 92 % of mountain areas of the country. Within these territories the safety of population can be achieved mainly by organizational activities. Approximately 7% of mountain areas have 1×10(-6) - 1×10(-4) individual risk values and require specific mitigation measures to protect people and infrastructure. Territories with individual risk values 1×10(-4) and above covers about 0,1 % of the territory and include the most severe and hazardous mountain areas. The whole specter of mitigation measures is required in order to minimize risk. The future development of such areas is not recommended

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

    International Nuclear Information System (INIS)

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

    2013-10-01

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

  17. Hotspot health physics codes used as a tool for managing excess risk on radiological emergencies

    International Nuclear Information System (INIS)

    Andrade, Edson Ramos de; Alves, Nelson Mendes; Rocha, Joao B.T.; Cruz, Ivana B. Manica da; Santos, Greice F. Fey dos; Machado, Michel Mansur; Rossato, Veronica Venturini; Bauermann, Liliane Freitas

    2008-01-01

    This work is aimed to use the Hotspot Health Physics codes in acute mode in order to estimate the immediate radiological impact associated with high acute radiation doses, which is applied to special target organs such as lung, small intestine wall, and red bone marrow. Organic compounds such as Diphenyl Diselenide (C 6 H 5 Se 2 C 6 H 5 ) and Ebselen (C 13 H 9 NOSe), an antioxidants selenium containing compounds, were used over irradiated phospholipids extracted from chicken yolk eggs, in vitro in order to reduce lipo-peroxidation. Experimental data were measured by Thiobarbituric Acid Reactive Substance (TBARS) assay which is able to measure the production of oxidative stress in the sample. Experimental data were extrapolated and applied as a reduction factors over equations for cancer excess risk calculation from BEIR V, for helping the decisonmaking process on Radiological Emergency Scenarios. (author)

  18. Competing risk theory and radiation risk assessment

    International Nuclear Information System (INIS)

    Groer, P.G.

    1980-01-01

    New statistical procedures are applied to estimate cumulative distribution functions (c.d.f.), force of mortality, and latent period for radiation-induced malignancies. It is demonstrated that correction for competing risks influences the shape of dose response curves, estimates of the latent period, and of the risk from ionizing radiations. The equivalence of the following concepts is demonstrated: force of mortality, hazard rate, and age or time specific incidence. This equivalence makes it possible to use procedures from reliability analysis and demography for radiation risk assessment. Two methods used by reliability analysts - hazard plotting and total time on test plots - are discussed in some detail and applied to characterize the hazard rate in radiation carcinogenesis. C.d.f.'s with increasing, decreasing, or constant hazard rate have different shapes and are shown to yield different dose-response curves for continuous irradiation. Absolute risk is shown to be a sound estimator only if the force of mortality is constant for the exposed and the control group. Dose-response relationships that use the absolute risk as a measure for the effect turn out to be special cases of dose-response relationships that measure the effect with cumulative incidence. (H.K.)

  19. Caries risk assessment in children

    DEFF Research Database (Denmark)

    Twetman, S

    2016-01-01

    PURPOSE: To summarise the findings of recent systematic reviews (SR) covering caries risk assessment in children, updated with recent primary studies. METHODS: A search for relevant papers published 2012-2014 was conducted in electronic databases. The systematic reviews were quality assessed...... displayed a high risk of bias. CONCLUSIONS: Based on the present summary of literature, it may be concluded: (1) a caries risk assessment should be carried out at the child's first dental visit and reassessments should be done during childhood (D); (2) multivariate models display a better accuracy than...... the use of single predictors and this is especially true for preschool children (C); (3) there is no clearly superior method to predict future caries and no evidence to support the use of one model, program, or technology before the other (C); and (4) the risk category should be linked to appropriate...

  20. Assessment of the radiological control at the IPEN radioisotope production facility

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  1. Assessment of the radiological control at the IPEN radioisotope production facility

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-10-30

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

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

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  4. Assessing Risk of Innovation

    International Nuclear Information System (INIS)

    Allgood, GO

    2001-01-01

    Today's manufacturing systems and equipment must perform at levels thought impossible a decade ago. Companies must push operations, quality, and efficiencies to unprecedented levels while holding down costs. In this new economy, companies must be concerned with market shares, equity growth, market saturation, and profit. U.S. manufacturing is no exception and is a prime example of businesses forced to adapt to constant and rapid changes in customer needs and product mixes, giving rise to the term ''Agile Manufacturing''. The survival and ultimate success of the American Manufacturing economy may depend upon its ability to create, innovate, and quickly assess the impact that new innovations will have on its business practices. Given the need for flexibility, companies need proven methods to predict and measure the impact that new technologies and strategies will have on overall plant performance from an enterprise perspective. The Value-Derivative Model provides a methodology and approach to assess such impacts in terms of energy savings, production increases, quality impacts, emission reduction, and maintenance and operating costs as they relate to enabling and emerging technologies. This is realized by calculating a set of first order sensitivity parameters obtained from expanding a Taylor Series about the system's operating point. These sensitivity parameters are invariant economic and operational indicators that quantify the impact of any proposed technology in terms of material throughput, efficiency, energy usage, environmental effects, and costs. These parameters also provide a mechanism to define metrics and performance measures that can be qualified in terms of real economic impact. Value-Derivative Analysis can be applied across all manufacturing and production segments of our economy and has found specific use in steel and textiles. Where economic models give the cost of conducting a business, Value-Derivative Analysis provides the cost to conduct

  5. Risk assessment research and technology assessment

    International Nuclear Information System (INIS)

    Albach, H.; Schade, D.; Sinn, H.

    1991-01-01

    The concepts and approaches for technology assessment, the targets and scientific principles, as well as recognizable deficits and recommendations concerning purposeful strategies for the promotion of this research field require a dialog between those concerned. Conception, deficits, and the necessary measures for risk assessment research and technology assessment were discussed as well as ethical aspects. The problematic nature of using organisms altered through genetic engineering in the open land, traffic and transport, site restoration, nuclear energy, and isotope applications were subjects particularly dealt with. (DG) [de

  6. Risk assessment for transport operations

    International Nuclear Information System (INIS)

    Appleton, P.R.; Miles, J.C.

    1990-01-01

    The world-wide safety of the transport of radioactive material is based on the IAEA Transport Regulations. Risk assessment can provide quantitative data to help in the demonstration, understanding and improvement of the effectiveness of the Regulations in assuring safety. In this Paper the methodology, data and computer codes necessary and available for transport risk assessment are reviewed. Notable examples of assessments carried out over the past 15 years are briefly described along with current research, and the benefits and limitations of the techniques are discussed. (author)

  7. 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

    Radiological Research Center) of RAMS was designated as the lead organization responsible for creating and maintaining the Registry. By December of 1991, when the USSR collapsed, the Registry database contained individual medical and dosimetric information for 659292 persons, of them 284919 were emergency workers. After disintegration of the Soviet Union the national Chernobyl registries were set up in Belarus, Russia and Ukraine. In Russia the registry operations are regulated by the Governmental Decree No 948 of 22 September 1993 'About national registration of persons exposed to radiation as a result of the Chernobyl accident and other radiation accidents and incidents'. As of January 1 2004, the Russian National Medical and Dosimetric Registry (RNMDR) contained individual medical and dosimetric data for 61,1819 persons, including 192148 emergency workers and 359724 residents of four contaminated oblasts of Russia (Bryansk, Kaluga, Oryol and Tula). Since the total number of subjects under study in the RNMDR is 6 times higher than in the Japanese registry, it may be concluded that the activities to assess actual radiation risks at low doses are well under way. The present book consists of two parts. The first part is devoted to emergency workers and the second to the population. The radiation-epidemiological studies described in the book cover the follow-up period from 1986 to 2001

  8. Radiological Impacts Assessment during Normal Decommissioning Operation for EU-APR

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Do Hyun; Lee, Keun Sung [KHNP CRI, Daejeon (Korea, Republic of); Lee, ChongHui [KEPCO Engineering and Construction, Gimcheon (Korea, Republic of)

    2016-10-15

    In this paper, radiological impacts on human beings during normal execution of the decommissioning operations from the current standard design of EU-APR which has been modified and improved from its original design of APR1400 to comply with EUR, are evaluated. Decommissioning is the final phase in the life cycle of a nuclear installation, covering all activities from shutdown and removal of fissile material to environmental restoration of the site. According to article 5.4 specified in chapter 2.20 of European Utility Requirements (EUR), all relevant radiological impacts on human being should be considered during the environmental assessment of decommissioning, including external exposure from direct radiation of plant and other radiation sources, and internal exposure due to inhalation and ingestion. In this paper, radiological impacts on human beings during normal circumstances of the decommissioning operation were evaluated from the current standard design of EU-APR based on the simple transport model and practical generic methodology for assessing the radiological impact provided by IAEA. The results of dose assessment fulfilled the dose limit for all scenarios.

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

    International Nuclear Information System (INIS)

    Mettler, F.A.

    2001-01-01

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

  10. Risk assessment and the environment

    International Nuclear Information System (INIS)

    Fisk, D.J.

    1992-01-01

    This paper reviews the use of risk assessment techniques in the field of environment protection. I will argue that in some important instances the development of environment policy has been a source of fruitful development of a risk based methodologies. In other cases the importation of risk assessment techniques has proved much more problematic. As the scope of environmental regulation increases so does the possibility of inconsistent and arbitrary solutions to problems. The need for a more systematic approach to the development of environmental regulation has never been stronger, so it is important to understand the reasons for the mixed success of risk assessment. This applies equally to those nations with long traditions of the regulation of private sector industry and those just beginning on this course. The way ahead may be to extend our ideas of how to express risk and uncertainty. Some of the recent cause celebres of environment policy show this challenge very clearly. As an example, this paper will look at the problem of assessing the risk of man-made climate change

  11. Risk assessment and the environment

    Energy Technology Data Exchange (ETDEWEB)

    Fisk, D J [Department of the Environment (United Kingdom)

    1992-07-01

    This paper reviews the use of risk assessment techniques in the field of environment protection. I will argue that in some important instances the development of environment policy has been a source of fruitful development of a risk based methodologies. In other cases the importation of risk assessment techniques has proved much more problematic. As the scope of environmental regulation increases so does the possibility of inconsistent and arbitrary solutions to problems. The need for a more systematic approach to the development of environmental regulation has never been stronger, so it is important to understand the reasons for the mixed success of risk assessment. This applies equally to those nations with long traditions of the regulation of private sector industry and those just beginning on this course. The way ahead may be to extend our ideas of how to express risk and uncertainty. Some of the recent cause celebres of environment policy show this challenge very clearly. As an example, this paper will look at the problem of assessing the risk of man-made climate change.

  12. Assessing Your Weight and Health Risk

    Science.gov (United States)

    ... Health Professional Resources Assessing Your Weight and Health Risk Assessment of weight and health risk involves using ... risk for developing obesity-associated diseases or conditions. Risk Factors for Health Topics Associated With Obesity Along ...

  13. Foetal Radiation Dose and Risk from Diagnostic Radiology Procedures: A Multinational Study

    International Nuclear Information System (INIS)

    Osei, Ernest K.; Darko, Johnson

    2012-01-01

    In diagnostic radiology examinations there is a benefit that the patient derives from the resulting diagnosis. Given that so many examinations are performed each year, it is inevitable that there will be occasions when an examination(s) may be inadvertently performed on pregnant patients or occasionally it may become clinically necessary to perform an examination(s) on a pregnant patient. In all these circumstances it is necessary to request an estimation of the foetal dose and risk. We initiated a study to investigate fetal doses from different countries. Exposure techniques on 367 foetuses from 414 examinations were collected and investigated. The FetDoseV4 program was used for all dose and risk estimations. The radiation doses received by the 367 foetuses ranges: <0.001–21.9 mGy depending on examination and technique. The associated probability of induced hereditary effect ranges: <1 in 200000000 (5 × 10 −9 ) to 1 in 10000 (1 × 10 −4 ) and the risk of childhood cancer ranges <1 in 12500000 (8 × 10 −8 ) to 1 in 500 (2 × 10 −3 ). The data indicates that foetal doses from properly conducted diagnostic radiology examinations will not result in any deterministic effect and a negligible risk of causing radiation induced hereditary effect in the descendants of the unborn child

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

    Science.gov (United States)

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

    2016-01-01

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

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

    International Nuclear Information System (INIS)

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

    1978-05-01

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

  16. Aspects regarding explosion risk assessment

    Directory of Open Access Journals (Sweden)

    Părăian Mihaela

    2017-01-01

    Full Text Available Explosive risk occurs in all activities involving flammable substances in the form of gases, vapors, mists or dusts which, in mixture with air, can generate an explosive atmosphere. As explosions can cause human losses and huge material damage, the assessment of the explosion risk and the establishment of appropriate measures to reduce it to acceptable levels according to the standards and standards in force is of particular importance for the safety and health of people and goods.There is no yet a recognized method of assessing the explosion risk, but regardless of the applied method, the likelihood of an explosive atmosphere occurrence has to be determined, together with the occurrence of an efficient ignition source and the magnitude of foreseeable consequences. In assessment processes, consequences analysis has a secondary importance since it’s likely that explosions would always involve considerable damage, starting from important material damages and up to human damages that could lead to death.The purpose of the work is to highlight the important principles and elements to be taken into account for a specific risk assessment. An essential element in assessing the risk of explosion in workplaces where explosive atmospheres may occur is technical installations and personal protective equipment (PPE that must be designed, manufactured, installed and maintained so that they cannot generate a source of ignition. Explosion prevention and protection requirements are governed by specific norms and standards, and a main part of the explosion risk assessment is related to the assessment of the compliance of the equipment / installation with these requirements.

  17. Risk assessment and nuclear power

    International Nuclear Information System (INIS)

    Bodansky, D.

    1982-01-01

    The range of risk perceptions involving nuclear power is so great that there is little hope of bridging extreme positions, but a consensus based upon reasoned discussion among uncommitted people could determine a sensible path. Our concerns over the uncertainties of risk assessment have made it increasingly difficult to make responsible decisions fast enough to deal with modern needs. The result is an immobility in energy matters that can point to a 2% reduction in oil use as its only triumph. The risk of nuclear war as a result of military action over energy issues suggests to some that the solution is to abolish nuclear power (however impractical) and to others that a rapid spread of nuclear power will eliminate energy as an incentive for war. If nuclear war is the major risk to consider, risk assessments need to include the risks of war, as well as those of carbon dioxide buildup and socio-economic disruptions, all of which loom larger than the risks of nuclear-plant accidents. Energy choices should be aimed at diminishing these major risks, even if they include the use of nuclear power. 26 references

  18. Sudden Cardiac Arrest (SCA) Risk Assessment

    Science.gov (United States)

    ... HRS Find a Specialist Share Twitter Facebook SCA Risk Assessment Sudden Cardiac Arrest (SCA) occurs abruptly and without ... people of all ages and health conditions. Start Risk Assessment The Sudden Cardiac Arrest (SCA) Risk Assessment Tool ...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-02-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-07-01

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

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

    International Nuclear Information System (INIS)

    Day, S.A.

    1989-01-01

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

  2. Preliminary survey for communicating risk in medical exposure. Perception of risk among nurses working in radiology

    International Nuclear Information System (INIS)

    Kanda, Reiko; Tsuji, Satsuki; Shirakawa, Yoshiyuki; Yonehara, Hidenori

    2008-01-01

    A questionnaire survey was conducted on radiation risk and medical exposure, particularly in applications involving children. The survey was targeted at nurses (170 females) engaged in important roles in communicating risk regarding medical exposure. The questionnaire survey yielded the following findings. A significant number of respondents associated the word radiation' with 'cancer treatment,' 'exposure,' and 'X-ray pictures.' Perceptions about 'food exposure' differed between respondents with children and those without. Among the potential health problems posed by radiation, effects on children,' 'cancer and leukemia,' and 'genetic effects' were perceived as the most worrisome. Significant differences in perception were noted regarding infertility between respondents with children and those without. Concerning the effects of medical exposure on fetuses/children, only 10 percent of all respondents replied that they were not anxious about negative effects in either case. Among the respondents who felt uneasy about these aspects, most tended to assess exposed parts, doses, damage potentially suffered, timing of occurrence, and uncertainty, based on their professional experience and knowledge, to rationally distinguish acceptable risks from unacceptable ones and to limit concern to the unacceptable aspects. (author)

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

    International Nuclear Information System (INIS)

    Pfingston, M.

    1998-01-01

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

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

    Science.gov (United States)

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

    2017-07-01

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

  5. NecroQuant: quantitative assessment of radiological necrosis

    Science.gov (United States)

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

    2017-11-01

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

  6. Human reliability assessment and probabilistic risk assessment

    International Nuclear Information System (INIS)

    Embrey, D.E.; Lucas, D.A.

    1989-01-01

    Human reliability assessment (HRA) is used within Probabilistic Risk Assessment (PRA) to identify the human errors (both omission and commission) which have a significant effect on the overall safety of the system and to quantify the probability of their occurrence. There exist a variey of HRA techniques and the selection of an appropriate one is often difficult. This paper reviews a number of available HRA techniques and discusses their strengths and weaknesses. The techniques reviewed include: decompositional methods, time-reliability curves and systematic expert judgement techniques. (orig.)

  7. Radiological hazard assessment of extracorporeal shock wave lithotripsy devices

    International Nuclear Information System (INIS)

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

    1987-01-01

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

  8. Environmental Risk Assessment of Nanomaterials

    Science.gov (United States)

    Bayramov, A. A.

    In this paper, various aspects of modern nanotechnologies and, as a result, risks of nanomaterials impact on an environment are considered. This very brief review of the First International Conference on Material and Information Sciences in High Technologies (2007, Baku, Azerbaijan) is given. The conference presented many reports that were devoted to nanotechnology in biology and business for the developing World, formation of charged nanoparticles for creation of functional nanostructures, nanoprocessing of carbon nanotubes, magnetic and optical properties of manganese-phosphorus nanowires, ultra-nanocrystalline diamond films, and nanophotonics communications in Azerbaijan. The mathematical methods of simulation of the group, individual and social risks are considered for the purpose of nanomaterials risk reduction and remediation. Lastly, we have conducted studies at a plant of polymeric materials (and nanomaterials), located near Baku. Assessments have been conducted on the individual risk of person affection and constructed the map of equal isolines and zones of individual risk for a plant of polymeric materials (and nanomaterials).

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

    Science.gov (United States)

    Agrawal, Yuvraj; Desai, Aravind; Mehta, Jaysheel

    2011-12-01

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

  10. Probabilistic risk assessment: Number 219

    International Nuclear Information System (INIS)

    Bari, R.A.

    1985-01-01

    This report describes a methodology for analyzing the safety of nuclear power plants. A historical overview of plants in the US is provided, and past, present, and future nuclear safety and risk assessment are discussed. A primer on nuclear power plants is provided with a discussion of pressurized water reactors (PWR) and boiling water reactors (BWR) and their operation and containment. Probabilistic Risk Assessment (PRA), utilizing both event-tree and fault-tree analysis, is discussed as a tool in reactor safety, decision making, and communications. (FI)

  11. The communication of radiological risk to populations exposed to a radiological accident: considerations concerning the accident in Goiania

    International Nuclear Information System (INIS)

    Curado, M.P.

    1996-01-01

    The main purpose of this paper is to describe the reactions of a population subjected to the effects of a radiological accident and receiving information about radiation effects for the first time. The behaviour of the victims during various phases of the accident is discussed. (author)

  12. Combined surgical and radiological intervention for complicated cholelithiasis in high-risk patients

    International Nuclear Information System (INIS)

    Gibney, R.G.; Fache, J.S.; Becker, C.D.; Nichols, D.M.; Cooperberg, P.L.; Stoller, J.L.; Burhenne, H.J.

    1987-01-01

    Surgical cholecystostomy under local infiltration anesthesia was combined with radiologic removal of gallstones in 36 high-risk patients with acute calculous gallbladder disease. At cholecystostomy, the fundus of the gallbladder was sutured to the anterior abdominal wall, permitting early percutaneous stone removal through the short surgical tract. All gallstones were removed in 31 of 36 patients, for an overall success rate of 86%. The success rate was 97% for gallbladder stones, 86% for cystic duct stones, and 63% for common bile duct stones which were removed by traversing the cystic duct. There were no deaths or serious complications

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

    International Nuclear Information System (INIS)

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

    1983-01-01

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

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

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  15. Developing RESRAD-BASELINE for environmental baseline risk assessment

    International Nuclear Information System (INIS)

    Cheng, Jing-Jy.

    1995-01-01

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

  16. Risk assessment using probabilistic standards

    International Nuclear Information System (INIS)

    Avila, R.

    2004-01-01

    A core element of risk is uncertainty represented by plural outcomes and their likelihood. No risk exists if the future outcome is uniquely known and hence guaranteed. The probability that we will die some day is equal to 1, so there would be no fatal risk if sufficiently long time frame is assumed. Equally, rain risk does not exist if there