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

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

International Nuclear Information System (INIS)

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

1995-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2014-07-01

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

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.

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

International Nuclear Information System (INIS)

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

2000-05-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2017-09-01

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

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

International Nuclear Information System (INIS)

Nes, Razvan; Benke, Roland R.

2008-01-01

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

Radiological consequence analysis of a repository for radioactive waste

International Nuclear Information System (INIS)

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

1982-01-01

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

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

International Nuclear Information System (INIS)

Little, M.S.

1982-05-01

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

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

International Nuclear Information System (INIS)

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

1993-12-01

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

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

International Nuclear Information System (INIS)

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

1989-07-01

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

Radiological Consequence Analyses Following a Hypothetical Severe Accident in Japan

Energy Technology Data Exchange (ETDEWEB)

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

2016-10-15

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

The Influence of atmospheric conditions to probabilistic calculation of impact of radiology accident on PWR 1000 MWe

International Nuclear Information System (INIS)

Pande Made Udiyani; Sri Kuntjoro

2015-01-01

The calculation of the radiological impact of the fission products releases due to potential accidents that may occur in the PWR (Pressurized Water Reactor) is required in a probabilistic. The atmospheric conditions greatly contribute to the dispersion of radionuclides in the environment, so that in this study will be analyzed the influence of atmospheric conditions on probabilistic calculation of the reactor accidents consequences. The objective of this study is to conduct an analysis of the influence of atmospheric conditions based on meteorological input data models on the radiological consequences of PWR 1000 MWe accidents. Simulations using PC-Cosyma code with probabilistic calculations mode, the meteorological data input executed cyclic and stratified, the meteorological input data are executed in the cyclic and stratified, and simulated in Muria Peninsula and Serang Coastal. Meteorological data were taken every hour for the duration of the year. The result showed that the cumulative frequency for the same input models for Serang coastal is higher than the Muria Peninsula. For the same site, cumulative frequency on cyclic input models is higher than stratified models. The cyclic models provide flexibility in determining the level of accuracy of calculations and do not require reference data compared to stratified models. The use of cyclic and stratified models involving large amounts of data and calculation repetition will improve the accuracy of statistical calculation values. (author)

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

International Nuclear Information System (INIS)

Funayama, Kyoko; Kajimoto, Mitsuhiro

2003-01-01

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

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)

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

International Nuclear Information System (INIS)

Chen Xiaoqiu; Yue Huiguo

2006-01-01

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

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

International Nuclear Information System (INIS)

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

2012-01-01

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

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

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

International Nuclear Information System (INIS)

Hill, M.D.; Lawson, G.

1980-11-01

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

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

International Nuclear Information System (INIS)

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

1978-01-01

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

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

International Nuclear Information System (INIS)

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

1996-01-01

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

Flammable gas deflagration consequence calculations for the tank waste remediation system basis for interim operation

Energy Technology Data Exchange (ETDEWEB)

Van Vleet, R.J., Westinghouse Hanford

1996-08-13

This paper calculates the radiological dose consequences and the toxic exposures for deflagration accidents at various Tank Waste Remediation System facilities. These will be used in support of the Tank Waste Remediation System Basis for Interim Operation.The attached SD documents the originator`s analysis only. It shall not be used as the final or sole document for effecting changes to an authorization basis or safety basis for a facility or activity.

Realistic methods for calculating the releases and consequences of a large LOCA

International Nuclear Information System (INIS)

Stephenson, W.; Dutton, L.M.C.; Handy, B.J.; Smedley, C.

1992-01-01

This report describes a calculational route to predict realistic radiological consequences for a successfully terminated large-loss-of-coolant accident (LOCA) at a pressurized-water reactor (PWR). All steps in the calculational route are considered. For each one, a brief comment is made on the significant differences between the methods of calculation that were identified in the benchmark studies and recommendations are made for the methods and data for carrying out realistic calculations. These are based on the best supportable methods and data and the technical basis for each recommendation is given. Where the lack of well-validated methods or data means that the most realistic method that can be justified is considered to be very conservative, the need for further research is identified. The behaviour of inorganic iodine and the removal of aerosols from the atmosphere of the reactor building are identified as areas of particular importance. Where the retention of radioactivity is sensitive to design features, these are identified and, for the most importance features, the impact of different designs on the release of activity is indicated. The predictions of the proposed model are calculated for each stage and compared with the releases of activity predicted by the licensing methods that were used in the earlier benchmark studies. The conservative nature of the latter is confirmed. Methods and data are also presented for calculating the resulting doses to members of the public of the National Radiological Protection Boards as a result of work carried out by several national bodies in the UK. Other, equally acceptable, models are used in other countries of the Community and some examples are given

Radiological consequences of the Chernobyl reactor accident

International Nuclear Information System (INIS)

Hill, P.; Hille, R.

2003-01-01

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

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

International Nuclear Information System (INIS)

Luykx, F.; Sinnaeve, J.

1986-01-01

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

Consequences of radiological emergencies at Goiania and Mayapuri

International Nuclear Information System (INIS)

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

2012-01-01

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

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

International Nuclear Information System (INIS)

Lucinio, Elena Albeira Guirado

2003-01-01

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

Radiological consequences of radioactive substances in building materials

International Nuclear Information System (INIS)

Tschurlovits, M.

1982-01-01

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

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

Consequence Assessment for Potential Scenarios of Radiological Terrorists Events

International Nuclear Information System (INIS)

Shin, Hyeongki; Kim, Juyoul

2007-01-01

Radiological dispersal device (RDD) means any method used to deliberately disperse radioactive material to create terror or harm. Dirty bomb is an example of RDD, which usually consists of radioactive material and unconventional explosive. Dirty bomb was a problem long before September 11, 2001. In 1987, the Iraqi government tested a one-ton radiological bomb. The Iraqi tests confirmed that a dirty bomb is not effective as weapons of mass destruction (WMD) and that its main value is as a psychological weapon. In 1995, Chechen rebels buried a dirty bomb in a park in Moscow threatening to detonate one in the future if their demands were not met. Another good example of potential dirty bomb effects was an incident in Goiania, Brazil on September 18, 1987, where an orphaned medical source containing 1,375 Ci of Cs-137 resulted the death of four people and extensive environmental contamination. The purposes of radiological terrorists events are not to destroy or damage the target but to disperse radioactivity in the environment. They inflict panic on a public and economic damage by disruption of business. They also have influence on enormous clean-up costs by spreading radioactive contamination including secondary impacts on water supply reservoirs. Generally, two major long-term concerns following a RDD are human health and economic impacts. In this study, we developed potential scenarios of radiological terrorists events and performed their radiological consequence assessments in terms of total effective dose equivalent (TEDE), projected cumulative external and internal dose, and ground deposition of radioactivity

Consequence Assessment for Potential Scenarios of Radiological Terrorists Events

Energy Technology Data Exchange (ETDEWEB)

Shin, Hyeongki [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of); Kim, Juyoul [Seoul National University, Seoul (Korea, Republic of)

2007-07-01

Radiological dispersal device (RDD) means any method used to deliberately disperse radioactive material to create terror or harm. Dirty bomb is an example of RDD, which usually consists of radioactive material and unconventional explosive. Dirty bomb was a problem long before September 11, 2001. In 1987, the Iraqi government tested a one-ton radiological bomb. The Iraqi tests confirmed that a dirty bomb is not effective as weapons of mass destruction (WMD) and that its main value is as a psychological weapon. In 1995, Chechen rebels buried a dirty bomb in a park in Moscow threatening to detonate one in the future if their demands were not met. Another good example of potential dirty bomb effects was an incident in Goiania, Brazil on September 18, 1987, where an orphaned medical source containing 1,375 Ci of Cs-137 resulted the death of four people and extensive environmental contamination. The purposes of radiological terrorists events are not to destroy or damage the target but to disperse radioactivity in the environment. They inflict panic on a public and economic damage by disruption of business. They also have influence on enormous clean-up costs by spreading radioactive contamination including secondary impacts on water supply reservoirs. Generally, two major long-term concerns following a RDD are human health and economic impacts. In this study, we developed potential scenarios of radiological terrorists events and performed their radiological consequence assessments in terms of total effective dose equivalent (TEDE), projected cumulative external and internal dose, and ground deposition of radioactivity.

Nuclear energy in Europe and its radiological consequences

International Nuclear Information System (INIS)

Kellerer, A.M.

1993-01-01

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

Radiological terrorism: problems of prevention and minimization of consequences

International Nuclear Information System (INIS)

Bolshov, Leonid; Arutyunyan, Rafael; Pavlovski, Oleg

2008-01-01

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

Radiological attacks and accidents. Medical consequences

International Nuclear Information System (INIS)

Sakuta, Hidenari

2007-01-01

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

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

International Nuclear Information System (INIS)

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

1998-01-01

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

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

International Nuclear Information System (INIS)

Bryant, P.M.

1979-01-01

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

Radiological environmental impacts from transportation of nuclear materials

International Nuclear Information System (INIS)

Shuai Zhengqing

1994-01-01

The author describes radiological impacts from transportation of nuclear materials. RADTRAN 4.0 supplied by IAEA was adopted to evaluate radiological consequence of incident-free transportation as well as the radiological risks from vehicular accidents occurring during transportation. The results of calculation show that the collective effective dose equivalent of incident-free transportation to the public and transportation workers is 7.94 x 10 -4 man·Sv. The calculated data suggest that the environmental impacts under normal and assumed accidental conditions are acceptable

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

International Nuclear Information System (INIS)

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

2008-01-01

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

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

International Nuclear Information System (INIS)

El-Kafas, A.A.

2011-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2017-09-15

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

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

International Nuclear Information System (INIS)

Hu Erbang; Gao Zhanrong; Zhang Heyuan; Wei Weiqiang

1996-12-01

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

The Fukushima accident: radiological consequences and first lessons. Proceedings

International Nuclear Information System (INIS)

2012-02-01

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

Preliminary radiological consequence estimate for a reference LEU core for PARR

International Nuclear Information System (INIS)

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

1988-07-01

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

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

International Nuclear Information System (INIS)

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

1984-01-01

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

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

International Nuclear Information System (INIS)

Manesse, D.; Crabol, B.

1988-04-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2014-05-15

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

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

International Nuclear Information System (INIS)

Drozdovich, V.V.

2000-01-01

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

An assessment of the radiological consequences of accidents in research reactors

International Nuclear Information System (INIS)

Ferreira, N.L.D.

1992-01-01

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

Parameter calculation tool for the application of radiological dose projection codes

International Nuclear Information System (INIS)

Galindo G, I. F.; Vergara del C, J. A.; Galvan A, S. J.; Tijerina S, F.

2016-09-01

The use of specialized codes to estimate the radiation dose projection to an emergency postulated event at a nuclear power plant requires that certain plant data be available according to the event being simulated. The calculation of the possible radiological release is the critical activity to carry out the emergency actions. However, not all of the plant data required are obtained directly from the plant but need to be calculated. In this paper we present a computational tool that calculates the plant data required to use the radiological dose estimation codes. The tool provides the required information when there is a gas emergency venting event in the primary containment atmosphere, whether well or dry well and also calculates the time in which the spent fuel pool would be discovered in the event of a leak of water on some of the walls or floor of the pool. The tool developed has mathematical models for the processes involved such as: compressible flow in pipes considering area change and for constant area, taking into account the effects of friction and for the case of the spent fuel pool hydraulic models to calculate the time in which a container is emptied. The models implemented in the tool are validated with data from the literature for simulated cases. The results with the tool are very similar to those of reference. This tool will also be very supportive so that in postulated emergency cases can use the radiological dose estimation codes to adequately and efficiently determine the actions to be taken in a way that affects as little as possible. (Author)

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

International Nuclear Information System (INIS)

Comte, N.; Bourgeois, L.

2001-01-01

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

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)

SHIELD 1.0: development of a shielding calculator program in diagnostic radiology

International Nuclear Information System (INIS)

Santos, Romulo R.; Real, Jessica V.; Luz, Renata M. da; Friedrich, Barbara Q.; Silva, Ana Maria Marques da

2013-01-01

In shielding calculation of radiological facilities, several parameters are required, such as occupancy, use factor, number of patients, source-barrier distance, area type (controlled and uncontrolled), radiation (primary or secondary) and material used in the barrier. The shielding design optimization requires a review of several options about the physical facility design and, mainly, the achievement of the best cost-benefit relationship for the shielding material. To facilitate the development of this kind of design, a program to calculate the shielding in diagnostic radiology was implemented, based on data and limits established by National Council on Radiation Protection and Measurements (NCRP) 147 and SVS-MS 453/98. The program was developed in C⌗ language, and presents a graphical interface for user data input and reporting capabilities. The module initially implemented, called SHIELD 1.0, refers to calculating barriers for conventional X-ray rooms. The program validation was performed by the comparison with the results of examples of shielding calculations presented in NCRP 147.

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

Energy Technology Data Exchange (ETDEWEB)

Dr. Bradley J Schrader

2009-03-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Dr. Bradley J Schrader

2010-10-01

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

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

International Nuclear Information System (INIS)

Schrader, Bradley J.

2009-01-01

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

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

International Nuclear Information System (INIS)

Savolainen, I.; Vuori, S.

1980-09-01

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

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

International Nuclear Information System (INIS)

Schmidt, Gerhard

2011-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-02-15

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

Radiological protection aspects of geological disposal of high-level radioactive waste

International Nuclear Information System (INIS)

Matsuzuru, Hideo; Kimura, Hideo

1992-01-01

A high-level radioactive waste, generated at a nuclear fuel reprocessing plant, will be disposed of deep, i.e., several hundred meters, within geological formations, to isolate it from the human environment. Since the waste contains significant amounts of long-lived radionuclides, such as Tc-99, I-129, Cs-135 and transuranic elements, the safety of its disposal, particularly as regards the requirement for the radiological protection of human and his environment even in the far future, is one of the essential subjects of all countries engaged in nuclear power production. The radiological protection system has long been established and applied to regulate radiation exposures to the public associated with a relatively short-term release of radioactive materials, during normal and accidental conditions, from nuclear installations such as a power plant and reprocessing plant. Radioactive waste disposal, which potentially offers a long-term radiological consequence on the public, inevitably produces a specific requirement, from the standpoint of radiological protection, that individuals and populations in the future should be accorded at least a current level of the protection. This requirement has caused a serious debate, among the community of radiological protection, on how to establish radiological protection standards and criteria, and how to establish safety assessment methodologies to demonstrate compliance with them. We have discussed in this paper on specific items such as numerical guides to indicate radiological consequences, time frames over which calculations of the consequences are to be carried out, uncertainties to be involved in the calculations, and safety assessment methodologies. (author)

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

International Nuclear Information System (INIS)

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

2016-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-07-15

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

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

International Nuclear Information System (INIS)

Grundfelt, Bertil

2013-07-01

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

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

International Nuclear Information System (INIS)

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

1981-01-01

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

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

International Nuclear Information System (INIS)

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

1998-01-01

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

Coupled calculation of the radiological release and the thermal-hydraulic behavior of a 3-loop PWR after a SGTR by means of the code RELAP5

Energy Technology Data Exchange (ETDEWEB)

Van Hove, W.; Van Laeken, K.; Bartsoen, L. [Belgatom, Brussels (Belgium)] [and others

1995-09-01

To enable a more realistic and accurate calculation of the radiological consequences of a SGTR, a fission product transport model was developed. As the radiological releases strongly depend on the thermal-hydraulic transient, the model was included in the RELAP5 input decks of the Belgian NPPs. This enables the coupled calculation of the thermal-hydraulic transient and the radiological release. The fission product transport model tracks the concentration of the fission products in the primary circuit, in each of the SGs as well as in the condenser. This leads to a system of 6 coupled, first order ordinary differential equations with time dependent coefficients. Flashing, scrubbing, atomisation and dry out of the break flow are accounted for. Coupling with the thermal-hydraulic calculation and correct modelling of the break position enables an accurate calculation of the mixture level above the break. Pre- and post-accident spiking in the primary circuit are introduced. The transport times in the FW-system and the SG blowdown system are also taken into account, as is the decontaminating effect of the primary make-up system and of the SG blowdown system. Physical input parameters such as the partition coefficients, half life times and spiking coefficients are explicitly introduced so that the same model can be used for iodine, caesium and noble gases.

Radiological consequences of the Chernobyl reactor accident

International Nuclear Information System (INIS)

Hill, P.; Hille, R.

2002-01-01

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

Critical evaluation of German regulatory specifications for calculating radiological exposure

Energy Technology Data Exchange (ETDEWEB)

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

2015-07-01

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

Offsite dose calculation manual guidance: Standard radiological effluent controls for boiling water reactors

International Nuclear Information System (INIS)

Meinke, W.W.; Essig, T.H.

1991-04-01

This report contains guidance which may be voluntarily used by licensees who choose to implement the provision of Generic Letter 89-- 01, which allows Radiological Effluent Technical Specifications (RETS) to be removed from the main body of the Technical Specifications and placed in the Offsite Dose Calculation Manual (ODCM). Guidance is provided for Standard Effluent Controls definitions, Controls for effluent monitoring instrumentation, Controls for effluent releases, Controls for radiological environmental monitoring, and the basis for Controls. Guidance on the formulation of RETS has been available in draft form for a number of years; the current effort simply recasts those RETS into Standard Radiological Effluent Controls for application to the ODCM. 11 tabs

Preliminary radiological consequence estimates for a reference LEU core for PARR

International Nuclear Information System (INIS)

Ali Khan, L.

1990-01-01

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

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

International Nuclear Information System (INIS)

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

1980-04-01

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

Offsite dose calculation manual guidance: Standard radiological effluent controls for pressurized water reactors

International Nuclear Information System (INIS)

Meinke, W.W.; Essig, T.H.

1991-04-01

This report contains guidance which may be voluntarily used by licensees who choose to implement the provision of Generic Letter 89-01, which allows Radiological Effect Technical Specifications (RETS) to be removed from the main body of the Technical Specifications and placed in the Offsite Dose Calculation Manual (ODCM). Guidance is provided for Standard Effluent Controls definitions, Controls for effluent monitoring instrumentation, Controls for effluent releases, Controls for radiological environmental monitoring, and the basis for Controls. Guidance on the formulation of RETS has been available in draft from (NUREG-0471 and -0473) for a number of years; the current effort simply recasts those RETS into Standard Radiological Effluent Controls for application to the ODCM. Also included for completeness are: (1) radiological environmental monitoring program guidance previously which had been available as a Branch Technical Position (Rev. 1, November 1979); (2) existing ODCM guidance; and (3) a reproduction of generic Letter 89-01

Estimating risk using bounding calculations and limited data

International Nuclear Information System (INIS)

COWLEY, W.L.

1999-01-01

This paper describes a methodology for estimating the potential risk to workers and the public from igniting organic solvents in any of the 177 underground waste storage tanks at the Hanford Site in southeastern Washington state. The Hanford Site is one of the U.S. Department of Energy's former production facilities for nuclear materials. The tanks contain mixed radioactive wastes. Risk is measured by calculating toxicological and radiological accident consequences and frequencies and comparing the results to established regulatory guidelines. Available sample data is insufficient to adequately characterize the waste and solvent, so a model that maximizes releases from the tanks (bounding case) is used. Maximizing releases (and thus consequences) is a standard technique used in safety analysis to compensate for lack of information. The model predicts bounding values of fire duration, the time at which the fire extinguishes because of lack of oxygen, and a pressure history of a fire in a tank. The model output is used to calculate mass and volume release rates of material from the tanks. The mass and volume release rates permit calculation of radiological and toxicological consequences. The resulting consequence calculations demonstrate that risk from an organic solvent fire in the tanks is within regulatory guidelines

Comparison of the radiological and chemical toxicity of lead

Energy Technology Data Exchange (ETDEWEB)

Beitel, G.A.; Mott, S.

1995-03-01

This report estimates the worst-case radiological dose to an individual from ingested lead containing picocurie levels of radionuclides and then compares the calculated radiological health effects to the chemical toxic effects from that same lead. This comparison provides an estimate of the consequences of inadvertently recycling, in the commercial market, lead containing nominally undetectable concentrations of radionuclides. Quantitative expressions for the radiological and chemical toxicities of lead are based on concentrations of lead in the blood stream. The result shows that the chemical toxicity of lead is a greater health hazard, by orders of magnitude, than any probable companion radiation dose.

Comparison of the radiological and chemical toxicity of lead

International Nuclear Information System (INIS)

Beitel, G.A.; Mott, S.

1995-03-01

This report estimates the worst-case radiological dose to an individual from ingested lead containing picocurie levels of radionuclides and then compares the calculated radiological health effects to the chemical toxic effects from that same lead. This comparison provides an estimate of the consequences of inadvertently recycling, in the commercial market, lead containing nominally undetectable concentrations of radionuclides. Quantitative expressions for the radiological and chemical toxicities of lead are based on concentrations of lead in the blood stream. The result shows that the chemical toxicity of lead is a greater health hazard, by orders of magnitude, than any probable companion radiation dose

Dispersion parameters: impact on calculated reactor accident consequences

Energy Technology Data Exchange (ETDEWEB)

Aldrich, D.C.

1979-01-01

Much attention has been given in recent years to the modeling of the atmospheric dispersion of pollutants released from a point source. Numerous recommendations have been made concerning the choice of appropriate dispersion parameters. A series of calculations has been performed to determine the impact of these recommendations on the calculated consequences of large reactor accidents. Results are presented and compared in this paper.

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

Energy Technology Data Exchange (ETDEWEB)

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

2017-11-15

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

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

International Nuclear Information System (INIS)

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

1977-01-01

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

Radiological assessment. A textbook on environmental dose analysis

Energy Technology Data Exchange (ETDEWEB)

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

1983-09-01

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

Radiological assessment. A textbook on environmental dose analysis

International Nuclear Information System (INIS)

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

1983-09-01

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

Evaluating risk using bounding calculations and limited data; TOPICAL

International Nuclear Information System (INIS)

COWLEY, W.L.

1999-01-01

This paper describes a methodology for estimating the potential risk to workers and the public from igniting organic solvents in any of the 177 underground waste storage tanks at the Hanford Site in southeastern Washington state. The Hanford Site is one of the U.S. Department of Energy's former production facilities for nuclear materials. The tanks contain mixed radioactive wastes. Risk is measured by calculating toxicological and radiological accident consequences and frequencies and comparing the results to established regulatory guidelines. Available sample data is insufficient to adequately characterize the waste and solvent, so a model that maximizes releases from the tanks (bounding case) is used. Maximizing releases (and thus consequences) is a standard technique used in safety analysis to compensate for lack of information. The model predicts bounding values of fire duration, the time at which the fire extinguishes because of lack of oxygen, and a pressure history of a fire in a tank. The model output is used to calculate mass and volume release rates of material from the tanks. The mass and volume release rates permit calculation of radiological and toxicological consequences. The resulting consequence calculations demonstrate that risk from an organic solvent fire in the tanks is within regulatory guidelines

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

International Nuclear Information System (INIS)

Kollas, J.G.

1985-01-01

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

Air and smear sample calculational tool for Fluor Hanford Radiological control

International Nuclear Information System (INIS)

BAUMANN, B.L.

2003-01-01

A spreadsheet calculation tool was developed to automate the calculations performed for determining the concentration of airborne radioactivity and smear counting as outlined in HNF--13536, Section 5.2.7, ''Analyzing Air and Smear Samples''. This document reports on the design and testing of the calculation tool. Radiological Control Technicians (RCTs) will save time and reduce hand written and calculation errors by using an electronic form for documenting and calculating work place air samples. Current expectations are RCTs will perform an air sample and collect the filter or perform a smear for surface contamination. RCTs will then survey the filter for gross alpha and beta/gamma radioactivity and with the gross counts utilize either hand calculation method or a calculator to determine activity on the filter. The electronic form will allow the RCT with a few key strokes to document the individual's name, payroll, gross counts, instrument identifiers; produce an error free record. This productivity gain is realized by the enhanced ability to perform mathematical calculations electronically (reducing errors) and at the same time, documenting the air sample

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

International Nuclear Information System (INIS)

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

1980-09-01

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

Data processing in radiology: Resume and prospects

Energy Technology Data Exchange (ETDEWEB)

Heilmann, H.P.; Tiemann, J.

1985-12-01

The technical aspects of radiology are particularly suitable for electronic data processing. In addition to automation of radiological apparatus and tumour registration, there are three areas in radiology particularly suitable for electronic data processing: treatment planning, dose calculations and supervision of radiotherapy techniques in radio-oncology. It can be used for work processing in the office and for documentation, both in diagnostic and therapeutic radiology, and digital techniques can be employed for image transmission, storage and manipulation. Computers for treatment planning and dose calculation are standard techniques and suitable computers allow one to spot occasional and systematic errors during radiation treation treatment and to eliminate these. They also provide for the automatic generation of the required protocols. Word processors have proved particularly valuable in private practice. They are valuable for composing reports from their basic elements, but less valuable for texts that are stereotypes. The most important developments are in digital imaging, image storage and image transmission. The storage of images on video discs, transmission through fibre-optic cables and computer manipulation of images are described and the consequences and problems, which may affect the radiologist, are discussed.

Data processing in radiology: Resume and prospects

International Nuclear Information System (INIS)

Heilmann, H.P.; Tiemann, J.

1985-01-01

The technical aspects of radiology are particularly suitable for electronic data processing. In addition to automation of radiological apparatus and tumour registration, there are three areas in radiology particularly suitable for electronic data processing: treatment planning, dose calculations and supervision of radiotherapy techniques in radio-oncology. It can be used for work processing in the office and for documentation, both in diagnostic and therapeutic radiology, and digital techniques can be employed for image transmission, storage and manipulation. Computers for treatment planning and dose calculation are standard techniques and suitable computers allow one to spot occasional and systematic errors during radiation treation treatment and to eliminate these. They also provide for the automatic generation of the required protocols. Word processors have proved particularly valuable in private practice. They are valuable for composing reports from their basic elements, but less valuable for texts that are stereotypes. The most important developments are in digital imaging, image storage and image transmission. The storage of images on video discs, transmission through fibre-optic cables and computer manipulation of images are described and the consequences and problems, which may affect the radiologist, are discussed. (orig.) [de

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

International Nuclear Information System (INIS)

Kollas, J.G.

1986-04-01

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

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

International Nuclear Information System (INIS)

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

1997-01-01

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

Environmental radiological consequences of a loss of coolant accident

International Nuclear Information System (INIS)

Guimaraes, A.C.F.

1981-01-01

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

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

CERN Document Server

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

1982-01-01

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

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

International Nuclear Information System (INIS)

1975-07-01

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

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

International Nuclear Information System (INIS)

2015-08-01

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

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

Directory of Open Access Journals (Sweden)

Rozental Jose de Julio

2002-01-01

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

Accident consequence calculations for project W-058 safety analysis

International Nuclear Information System (INIS)

Van Keuren, J.C.

1997-01-01

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

The application research of MACCS in consequence assessment of the attacked Dayabay Nuclear Power Station

International Nuclear Information System (INIS)

Zhao Yuan; Dong Binjiang

2003-01-01

The method of radiological consequence assessment as Dayabay nuclear power station being attacked in war is studied in this paper. The Models and software of calculation and the parameters which have been chosen are also studied in this paper. This study estimates the off-site consequences of two different types of being attack accidents spectrum and the spent fuel pool being attacked accidents spectrum. This study calculated the distributing of radiological consequence in different weather. According to the analyse of the consequence, we get such result that the radiate consequence of nuclear reactor of Daya Bay nuclear power plant being attack in war is the same as the consequence of nuclear accident, but the consequence of spent fuel pool being attacked is very serious. If the spent fuel pool was attacked by the enemy, the contaminated area is very large. The effective dose within 30 km under the wind will exceed 1 Sv. Based in part upon the above information the recommendation is made that the Daya Bay nuclear power plant should be closed or run in low power. and the nuclear island should be protected in war. (authors)

Federal support of radiological research

International Nuclear Information System (INIS)

Hendee, W.R.

1981-01-01

Pervading the plans and objective outlined herein for continued and enhanced federal support of research in radiology is a challenge of unparalleled magnitude, for the economic foundation on which this support is based has rarely been more precarious. The new administration in Washington may well be the most fiscally constrained in half a century, and its stated interest in reducing federal expenditures could have disastrous consequences for the scientific research effort in this country, including that in radiology and the radiological sciences. The circumvention of these consequences may well require the dedicated effort of the entire scientific community over the next few months and years, including that part representing radiology and the radiological sciences

Experimental method for calculation of effective doses in interventional radiology; Metodo experimental para calculo de dosis efectivas en radiologia intervencionista

Energy Technology Data Exchange (ETDEWEB)

Herraiz Lblanca, M. D.; Diaz Romero, F.; Casares Magaz, O.; Garrido Breton, C.; Catalan Acosta, A.; Hernandez Armas, J.

2013-07-01

This paper proposes a method that allows you to calculate the effective dose in any interventional radiology procedure using an anthropomorphic mannequin Alderson RANDO and dosimeters TLD 100 chip. This method has been applied to an angio Radiology procedure: the biliary drainage. The objectives that have been proposed are: to) put together a method that, on an experimental basis, allows to know dosis en organs to calculate effective dose in complex procedures and b) apply the method to the calculation of the effective dose of biliary drainage. (Author)

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

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-02-15

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

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

International Nuclear Information System (INIS)

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

1980-01-01

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

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

International Nuclear Information System (INIS)

Jacquier, P.

1989-01-01

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

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

International Nuclear Information System (INIS)

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

2012-01-01

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

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

International Nuclear Information System (INIS)

Kocar, Cemil; Soekmen, Cemal Niyazi

2009-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2002-12-01

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

Introduction of radiological protection; Pengenalan kepada perlindungan radiologi

Energy Technology Data Exchange (ETDEWEB)

NONE

1988-12-31

The chapter briefly discussed the following subjects: basic principles of radiological protection , dose limit which was suggested, stochastic and nonstochastic effects, equivalent dose and alternative of it`s calculation, limit for the publics, ICRP (International Commission for Radiological Protection) recommendations, and the principles of radiological protection. Dangerous radiation sources also briefly summarized i.e. x-ray generators, reactor nucleus.

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

Energy Technology Data Exchange (ETDEWEB)

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

1996-12-31

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

Ventilation system consequence calculations to support salt well pumping single-shell tank 241-A-101

Energy Technology Data Exchange (ETDEWEB)

Ryan, G.W.

1997-05-07

This document presents the radiological dose and toxicological exposure calculations for an accident scenario involved with the ventilation system used to support salt well pumping single-shell tank 241-A-101. This tank has been listed on the Hydrogen Watch List.

Ventilation system consequence calculations to support salt well pumping single-shell tank 241-A-101

International Nuclear Information System (INIS)

Ryan, G.W.

1997-01-01

This document presents the radiological dose and toxicological exposure calculations for an accident scenario involved with the ventilation system used to support salt well pumping single-shell tank 241-A-101. This tank has been listed on the Hydrogen Watch List

Possibilities of radiologic diagnosis of pancreatic calcinosis and chronic calculous pancreatics

International Nuclear Information System (INIS)

Loginov, A.S.; Sivash, Eh.S.; Kudryavtseva, G.V.

1982-01-01

X-ray diagnosis of the pancreatic gland calculous damage as well as chronic pancreatitis have been studied in 23 patients. A methodologic approach to examination of this group of patients was defined. Posteroanterior radiography has been shown to be of decisive importance in diagnosis of the calcified pancreatic gland. Duodenography and choleduodenography both considerably promote recognition of chronic pancreatitis. The radiologic method also allows one to reveal a series of complications: the common bile duct compression, duodenal stenosis, pancreatic tumor in the presence of chronic pancreatitis, malabsorption syndrome

Effective doses in paediatric radiology

International Nuclear Information System (INIS)

Iacob, Olga; Diaconescu, Cornelia; Roca, Antoaneta

2001-01-01

Because of their longer life expectancy, the risk of late manifestations of detrimental radiation effects is greater in children than in adults and, consequently, paediatric radiology gives ground for more concern regarding radiation protection than radiology of adults. The purpose of our study is to assess in terms of effective doses the magnitude of paediatric patient exposure during conventional X-ray examinations, selected for their high frequency or their relatively high doses to the patient. Effective doses have been derived from measurements of dose-area product (DAP) carried out on over 900 patients undergoing X-ray examinations, in five paediatric units. The conversion coefficients for estimating effective doses are those calculated by the NRPB using Monte-Carlo technique on a series of 5 mathematical phantoms representing 0, 1, 5, 10 and 15 year old children. The annual frequency of X-ray examinations necessary for collective dose calculation are those reported in our last national study on medical exposure, conducted in 1995. The annual effective doses from all medical examinations for the average paediatric patient are as follows: 1.05 mSv for 0 year old, 0.98 mSv for 1 year old, 0.53 mSv for 5 year old, 0.65 mSv for 10 year old and 0.70 mSv for 15 year old. The resulting annual collective effective dose was evaluated at 625 man Sv with the largest contribution of pelvis and hip examinations (34%). The annual collective effective associated with paediatric radiology in Romania represent 5% of the annual value resulting from all diagnostic radiology. Examination of the chest is by far the most frequent procedure for children, accounting for about 60 per cent of all annually performed X-ray conventional examinations. Knowledge of real level of patient dose is an essential component of quality assurance programs in paediatric radiology. (authors)

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

International Nuclear Information System (INIS)

Imanaka, T.

1998-03-01

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

Legislation in Ukraine about the radiological consequences of the Chernobyl accident

International Nuclear Information System (INIS)

Nasvit, O.

1998-01-01

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

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

International Nuclear Information System (INIS)

Wenzel, D.R.

1994-02-01

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

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

International Nuclear Information System (INIS)

Lee, Joung Hoon; Yu, Dong Han

2010-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2010-10-15

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

PLUTONIUM/HIGH-LEVEL VITRIFIED WASTE BDBE DOSE CALCULATION

Energy Technology Data Exchange (ETDEWEB)

J.A. Ziegler

2000-11-20

The purpose of this calculation is to provide a dose consequence analysis of high-level waste (HLW) consisting of plutonium immobilized in vitrified HLW to be handled at the proposed Monitored Geologic Repository at Yucca Mountain for a beyond design basis event (BDBE) under expected conditions using best estimate values for each calculation parameter. In addition to the dose calculation, a plutonium respirable particle size for dose calculation use is derived. The current concept for this waste form is plutonium disks enclosed in cans immobilized in canisters of vitrified HLW (i.e., glass). The plutonium inventory at risk used for this calculation is selected from Plutonium Immobilization Project Input for Yucca Mountain Total Systems Performance Assessment (Shaw 1999). The BDBE examined in this calculation is a nonmechanistic initiating event and the sequence of events that follow to cause a radiological release. This analysis will provide the radiological releases and dose consequences for a postulated BDBE. Results may be considered in other analyses to determine or modify the safety classification and quality assurance level of repository structures, systems, and components. This calculation uses best available technical information because the BDBE frequency is very low (i.e., less than 1.0E-6 events/year) and is not required for License Application for the Monitored Geologic Repository. The results of this calculation will not be used as part of a licensing or design basis.

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

International Nuclear Information System (INIS)

Preston, A.

1975-01-01

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

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

International Nuclear Information System (INIS)

Kollas, J.G.

1985-09-01

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

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

International Nuclear Information System (INIS)

Jacquier, P.; Raimbault, P.

1989-07-01

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

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

International Nuclear Information System (INIS)

Woollam, P.B.

1984-08-01

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

Estimation of health hazards resulting from a radiological terrorist attack in a city

DEFF Research Database (Denmark)

Andersson, Kasper Grann; Mikkelsen, Torben; Astrup, Poul

2008-01-01

on accidental exposure. The aim of the present study was to illustrate issues that need to be considered in evaluating the radiological consequences of a 'dirty bomb' explosion. This is done through a worked example of simplified calculations of relative dose contributions for a specific 'dirty bomb' scenario...

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

International Nuclear Information System (INIS)

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

2010-01-01

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

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

International Nuclear Information System (INIS)

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

1979-01-01

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

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

International Nuclear Information System (INIS)

Himes, D.A.

1997-01-01

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

Confidence level in the calculations of HCDA consequences using large codes

International Nuclear Information System (INIS)

Nguyen, D.H.; Wilburn, N.P.

1979-01-01

The probabilistic approach to nuclear reactor safety is playing an increasingly significant role. For the liquid-metal fast breeder reactor (LMFBR) in particular, the ultimate application of this approach could be to determine the probability of achieving the goal of a specific line-of-assurance (LOA). Meanwhile a more pressing problem is one of quantifying the uncertainty in a calculated consequence for hypothetical core disruptive accident (HCDA) using large codes. Such uncertainty arises from imperfect modeling of phenomenology and/or from inaccuracy in input data. A method is presented to determine the confidence level in consequences calculated by a large computer code due to the known uncertainties in input invariables. A particular application was made to the initial time of pin failure in a transient overpower HCDA calculated by the code MELT-IIIA in order to demonstrate the method. A probability distribution function (pdf) for the time of failure was first constructed, then the confidence level for predicting this failure parameter within a desired range was determined

Radiological shielding of low power compact reactor: calculation and design

International Nuclear Information System (INIS)

Marino, Raul

2004-01-01

The development of compact reactors becoming a technology that offers great projection and innumerable use possibilities, both in electricity generation and in propulsion.One of the requirements for the operation of this type of reactor is that it must include a radiological shield that will allow for different types of configurations and that, may be moved with the reactor if it needs to be transported.The nucleus of a reactor emits radiation, mainly neutrons and gamma rays in the heat of power, and gamma radiation during the radioactive decay of fission products.This radiation must be restrained in both conditions of operation to avoid it affecting workers or the public.The combination of different materials and properties in layers results in better performance in the form of a decrease in radiation, hence causing the dosage outside the reactor, whether in operation or shut down, to fall within the allowed limits.The calculations and design of radiological shields is therefore of paramount importance in reactor design.The choice of material and the design of the shield have a strong impact on the cost and the load capacity, the latter being one of the characteristics to optimize.The imposed condition of design is that the reactor can be transported together with the decay shield in a standard container of 40 foot [es

Radiological safety evaluation for a Waste Transfer Facility at Savannah River Site

International Nuclear Information System (INIS)

Ades, M.J.

1993-01-01

This paper provides a review of the radiological safety evaluation performed for a Waste Transfer Facility (WTF) located at the Savannah River Site (SRS). This facility transfers liquid radioactive waste between various waste processing facilities and waste storage facilities. The WTF includes functional components such as the diversion box and the pump pits, waste transfer lines, and the outside yard service piping and electrical services. The WSRC methodology is used to evaluate the consequences of postulated accidents that result in the release of radioactive material. Such accidents include transfer line breaks, underground liquid pathway release, fire in pump tank cells and HEPA filters, accidents due to natural phenomena, and externally induced events. Chemical hazards accidents are not considered. The analysis results indicate that the calculated mean onsite and offsite radiological consequences are bounded by the corresponding WSRC dose limits for each accident considered. Moreover, the results show that the maximum onsite and offsite doses calculated for the WTF are lower than the maximum doses determined for the whole radioactive waste facility where the WTF is located

Radiological consequences of possible irradiation scenarios in military practice in Ukraine

International Nuclear Information System (INIS)

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

2017-01-01

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

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

International Nuclear Information System (INIS)

Savino, A.V.

1995-11-01

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

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

International Nuclear Information System (INIS)

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

1994-01-01

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

Radiological and chemical source terms for Solid Waste Operations Complex

International Nuclear Information System (INIS)

Boothe, G.F.

1994-01-01

The purpose of this document is to describe the radiological and chemical source terms for the major projects of the Solid Waste Operations Complex (SWOC), including Project W-112, Project W-133 and Project W-100 (WRAP 2A). For purposes of this document, the term ''source term'' means the design basis inventory. All of the SWOC source terms involve the estimation of the radiological and chemical contents of various waste packages from different waste streams, and the inventories of these packages within facilities or within a scope of operations. The composition of some of the waste is not known precisely; consequently, conservative assumptions were made to ensure that the source term represents a bounding case (i.e., it is expected that the source term would not be exceeded). As better information is obtained on the radiological and chemical contents of waste packages and more accurate facility specific models are developed, this document should be revised as appropriate. Radiological source terms are needed to perform shielding and external dose calculations, to estimate routine airborne releases, to perform release calculations and dose estimates for safety documentation, to calculate the maximum possible fire loss and specific source terms for individual fire areas, etc. Chemical source terms (i.e., inventories of combustible, flammable, explosive or hazardous chemicals) are used to determine combustible loading, fire protection requirements, personnel exposures to hazardous chemicals from routine and accident conditions, and a wide variety of other safety and environmental requirements

Legal aspects of nuclear and radiological accidents

International Nuclear Information System (INIS)

El-baroudy, M.M.

2005-01-01

Aiming at preventing nuclear and radiological accidents and maintaining safety and security, the State extends its jurisdiction over nuclear and radiological activities through the promulgation of regulatory legislations and providing criminal protection to these activities. The State, in its legislation, defines an authority responsible for the planning of preparedness for emergency situations. That Authority cooperates with other competent authorities in the State as well as with other relevant international organizations and other States in a coordinated way aiming at dealing effectively with and mitigating the consequences of nuclear and radiological accidents through promulgating relevant international conventions and plans for reinforcement of international cooperation in accidents situations. Moreover, the International Atomic Energy Authority (IAEA) can provide specialized consultations and offer assistance in case of accidents. The present study is divided into an introduction and two chapters. In the introduction, the nature of nuclear or radiological accidents is defined. The first chapter deals with the national legal system for preventing the occurrence of nuclear and radiological accidents and mitigating their consequences. The second chapter deals with the international cooperation for facing nuclear or radiological accidents and mitigating their consequences

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

International Nuclear Information System (INIS)

2010-01-01

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

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.

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

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

International Nuclear Information System (INIS)

2011-12-01

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

Formation of decontamination cost calculation model for severe accident consequence assessment

International Nuclear Information System (INIS)

Silva, Kampanart; Promping, Jiraporn; Okamoto, Koji; Ishiwatari, Yuki

2014-01-01

In previous studies, the authors developed an index “cost per severe accident” to perform a severe accident consequence assessment that can cover various kinds of accident consequences, namely health effects, economic, social and environmental impacts. Though decontamination cost was identified as a major component, it was taken into account using simple and conservative assumptions, which make it difficult to have further discussions. The decontamination cost calculation model was therefore reconsidered. 99 parameters were selected to take into account all decontamination-related issues, and the decontamination cost calculation model was formed. The distributions of all parameters were determined. A sensitivity analysis using the Morris method was performed in order to identify important parameters that have large influence on the cost per severe accident and large extent of interactions with other parameters. We identified 25 important parameters, and fixed most negligible parameters to the median of their distributions to form a simplified decontamination cost calculation model. Calculations of cost per severe accident with the full model (all parameters distributed), and with the simplified model were performed and compared. The differences of the cost per severe accident and its components were not significant, which ensure the validity of the simplified model. The simplified model is used to perform a full scope calculation of the cost per severe accident and compared with the previous study. The decontamination cost increased its importance significantly. (author)

IAEA Perspectives on Radiological Characterisation

International Nuclear Information System (INIS)

O'Sullivan, Patrick; Ljubenov, Vladan

2012-01-01

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

Dose calculation for accident situations at WWR-S type spent nuclear fuel repository

International Nuclear Information System (INIS)

Margeanu, S.; Florescu, G.

2006-01-01

Full text: The Spent Nuclear Fuel Repository at IFIN-HH Bucharest (SNFR IFIN-HH) consists in four pools, repository hall, radiological monitoring system, ventilation system and auxiliary systems. At the moment the remaining activity in the repository is about 3500 Ci. Despite of the small activity, for emergency preparedness purposes, several accident scenarios, with a non zero probability of occurrence during the repository lifetime, have been postulated. Evaluations of radiological consequences to personnel, general public and environment, for each accident scenario have been performed. The radioactive inventory was evaluated with ORIGEN code from SCALE computer code system and radiological consequences were evaluated with COSYMA computer code. Assumptions for the source term determination, meteorological conditions and release, are presented. The calculated values of doses and risk are also presented. The impact of these accident scenarios on population and environment is also discussed. (authors)

Radiological accidents: education for prevention and confrontation

International Nuclear Information System (INIS)

Cardenas Herrera, Juan; Fernandez Gomez, Isis Maria

2008-01-01

The purpose of this work is to train and inform on radiological accidents as a preventive measure to improve the people life quality. Radiological accidents are part of the events of technological origin which are composed of nuclear and radiological accidents. As a notable figure is determined that there have been 423 radiological accidents from 1944 to 2005 and among the causes prevail industrial accidents, by irradiations, medical accidents and of laboratories, among others. Latin American countries such as Argentina, Brazil, Mexico and Peru are some where most accidents have occurred by radioactivity. The radiological accidents can have sociological, environmental, economic, social and political consequences. In addition, there are scenarios of potential nuclear accidents and in them the potential human consequences. Also, the importance of the organization and planning in a nuclear emergency is highlighted. Finally, the experience that Cuba has lived on the subject of radiological accidents is described [es

Radiological consequences of gas and oil extraction

International Nuclear Information System (INIS)

Kutkov, V.

2002-01-01

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

ATMOSPHERIC DISPERSION COEFFICIENTS AND RADIOLOGICAL AND TOXICOLOGICAL EXPOSURE METHODOLOGY FOR USE IN TANK FARMS

Energy Technology Data Exchange (ETDEWEB)

GRIGSBY KM

2011-04-07

This report presents the atmospheric dispersion coefficients used in Tank Farms safety analysis. The basis equations for calculating radiological and toxicological exposures are also included. In this revision, the time averaging for toxicological consequence evaluations is clarified based on a review of DOE complex guidance and a review of tank farm chemicals.

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

International Nuclear Information System (INIS)

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

1996-08-01

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

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

International Nuclear Information System (INIS)

Chan, S.H.

1977-01-01

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

Review of specific radiological accident considerations

International Nuclear Information System (INIS)

Elder, J.

1984-01-01

Specific points of guidance provided in the forthcoming document A Guide to Radiological Accident Considerations for Siting and Design of Nonreactor Nuclear Facilities are discussed. Of these, the following are considered of particular interest to analysts of hypothetical accidents: onsite dose limits; population dose, public health effects, and environmental contamination as accident consequences which should be addressed; risk analysis; natural phenomena as accident initiators; recommended dose models; multiple organ equivalent dose; and recommended methods and parameters for source terms and release amount calculations. Comments are being invited on this document, which is undergoing rewrite after the first stage of peer review

Radiological optimization

International Nuclear Information System (INIS)

Zeevaert, T.

1998-01-01

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

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

CERN Document Server

Kelly, G N

1983-01-01

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

Radiological impacts of uranium recovery in the phosphate industry

International Nuclear Information System (INIS)

Ryan, M.T.

1981-01-01

This article characterizes the occupational and public radiological health impacts associated with phosphate mining and milling. These impacts are related to the phosphate industry's uranium production potential and are compared with those associated with conventional uranium mining and milling. The radiological impacts resulting from occupational and nonoccupational exposures are assessed. Occupational exposures in phosphate facilities are compared to background exposures and radiological population dose assessments, which characterize important radionuclides and exposure pathways. The following conclusions were reached: (1) public consequences of phosphate mining will occur whether or not uranium is recovered as a by-product, (2) radiological consequences of phosphate mining may be comparable to those associated with uranium mining and milling per unit uranium production, (3) radiological impacts via surface waterways and crops fertilized with uranium-bearing phosphates are of minor consequence, and (4) major radiological public health problems associated with phosphate mining are related to radon and radon progeny exposures in structures built on reclaimed lands or with phosphate mining residues, although the magnitudes of these impacts are difficult to evaluate with current data

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

International Nuclear Information System (INIS)

Maul, P.R.

1983-01-01

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

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

International Nuclear Information System (INIS)

Jacquier, P.; Raimbault, P.

1990-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1990-01-01

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

User guide programmer's reference. NUDOS: A computer programme for assessing the consequences of airborne releases of radionuclides

International Nuclear Information System (INIS)

Grupa, J.

1996-10-01

NUDOS is a computer program that can be used to evaluate the consequences of airborne releases of radioactive materials. The consequences evaluated are individual dose and associated radiological risk, collective dose and the contamination of land. The code is capable of dealing with both routine and accidental releases. For accidental releases both deterministic and probabilistic calculations can be performed and the impact and effectiveness of emergency actions can be evaluated. (orig.)

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

A methodology for radiological accidents analysis in industrial gamma radiography

International Nuclear Information System (INIS)

Silva, F.C.A. da.

1990-01-01

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

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

International Nuclear Information System (INIS)

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

2011-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2017-10-02

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2000-12-01

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

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

International Nuclear Information System (INIS)

Homma, Toshimitsu

2000-12-01

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

Medical social consequences of the safety problems of oncological radiology

International Nuclear Information System (INIS)

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

2015-01-01

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

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

International Nuclear Information System (INIS)

Vieru, Gheorghe

2008-01-01

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

Calculation of conversion coefficients for radiological protection against external radiation exposures

International Nuclear Information System (INIS)

Zankl, M.

2001-01-01

Calculations are essential for radiation protection practice because organ doses and effective doses cannot be measured directly. Conversion coefficients describe the numerical relationships of protection quantities and operational quantities. The latter can be measured in practical situations using suitable dosimeters. The conversion coefficients are calculated using radiation transport codes - usually based on Monte Carlo methods - that simulate the interactions of radiation with matter in computational models of the human body. A new generation of human body models, the so-called voxel models, are constructed from image data of real persons using suitable image processing systems, consequently, they represent the human anatomy more realistically than the so-called mathematical models. The numerical effects of realistic body anatomy on the calculated conversion coefficients can amount to 70% and more for external exposures. (orig.) [de

Rational use of diagnostic radiology

International Nuclear Information System (INIS)

Racoveanu, N.T.; Volodin, V.

1992-01-01

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

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

International Nuclear Information System (INIS)

Grodzinsky, D.M.

1998-01-01

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

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

International Nuclear Information System (INIS)

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

2008-01-01

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

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)

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

International Nuclear Information System (INIS)

Kelly, G.N.

1990-01-01

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

Concepts of optimisation and justification consequences for radiological mass screening

International Nuclear Information System (INIS)

Carmichael, J.H.E.

1987-01-01

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

Dosimetry in diagnosis examinations in radiology

International Nuclear Information System (INIS)

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

2003-01-01

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

Accidental releases of radionuclides: a preliminary study of the consequences of land contamination

International Nuclear Information System (INIS)

Simmonds, J.R.; Haywood, S.M.; Linsley, G.S.

1982-10-01

The long term consequences of land contamination from accidental releases of activity from thermal reactors are examined. The radiological consequences are assessed using an analysis of the exposure of individuals and the population to ground deposits of the radionuclides released. The contribution of the different nuclides in the release by their various exposure routes to the irradiation of man are calculated as a function of time after release and the most radiologically important are identified. A preliminary assessment is made of off-site economic and social consequences of accidental releases by estimating the areas of land which would be affected by the introduction of countermeasures to control individual radiation exposure due to external irradiation from ground deposits (relocation of populations), and the intake of radionuclides contained in locally produced foodstuffs (restrictions on food production). The areas where administrative controls would be necessary decline in size with time after the release; estimates are made of this time-dependent behaviour using dynamic environmental transfer models. Finally, the collective doses saved by the introduction of countermeasures are estimated using population and agricultural distribution data for a rural location in the United Kingdom. (author)

Planning for a radiological emergency in health care institutions

International Nuclear Information System (INIS)

Jerez Vegueria, S.F.; Jerez Vegueria, P.F.

1998-01-01

The possible occurrence of accidents involving sources of ionizing radiation calls for response plans to mitigate the consequences of radiological accidents. An emergency planning framework is suggested for institutions which use medical applications of ionizing radiation. Bearing in mind that the prevention of accidents is of prime importance in dealing with radioactive materials and other sources of ionizing radiation, it is recommended that emergency instructions and procedures address certain aspects of the causes of these radiological events. Issues such as identification of radiological events in medical practices and their consequences, protective measures, planning for an emergency response and maintenance of emergency capacity are considered. (author)

Unenhanced computed tomography in acute renal colic reduces cost outside radiology department

DEFF Research Database (Denmark)

Lauritsen, J.; Andersen, J.R.; Nordling, J.

2008-01-01

BACKGROUND: Unenhanced multidetector computed tomography (UMDCT) is well established as the procedure of choice for radiologic evaluation of patients with renal colic. The procedure has both clinical and financial consequences for departments of surgery and radiology. However, the financial effect...... outside the radiology department is poorly elucidated. PURPOSE: To evaluate the financial consequences outside of the radiology department, a retrospective study comparing the ward occupation of patients examined with UMDCT to that of intravenous urography (IVU) was performed. MATERIAL AND METHODS......) saved the hospital USD 265,000 every 6 months compared to the use of IVU. CONCLUSION: Use of UMDCT compared to IVU in patients with renal colic leads to cost savings outside the radiology department Udgivelsesdato: 2008/12...

The Risoe model for calculating the consequences of the release of radioactive material to the atmosphere

International Nuclear Information System (INIS)

Thykier-Nielsen, S.

1980-07-01

A brief description is given of the model used at Risoe for calculating the consequences of releases of radioactive material to the atmosphere. The model is based on the Gaussian plume model, and it provides possibilities for calculation of: doses to individuals, collective doses, contamination of the ground, probability distribution of doses, and the consequences of doses for give dose-risk relationships. The model is implemented as a computer program PLUCON2, written in ALGOL for the Burroughs B6700 computer at Risoe. A short description of PLUCON2 is given. (author)

Patient exposure in paediatric radiology

International Nuclear Information System (INIS)

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

2002-01-01

Because of their longer life expectancy, the risk of late manifestations of detrimental radiation effects is greater in children than in adults and, consequently, paediatric radiology gives ground for more concern regarding radiation protection than radiology of adults. The purpose of our study was to assess, in terms of effective dose, the magnitude of paediatric patient exposure during conventional X-ray examinations, selected for their high frequency or their relatively high doses delivered to patient

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

International Nuclear Information System (INIS)

Woollam, P.B.

1985-05-01

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

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

International Nuclear Information System (INIS)

Palsson, S.E.

2002-11-01

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

SSI's independent consequence calculations in support of the regulatory review of the SR-Can safety assessment

International Nuclear Information System (INIS)

Shulan Xu; Dverstorp, Bjoern; Woerman, Anders; Marklund, Lars; Klos, Richard; Shaw, George

2008-03-01

With the publication of the SR-Can report at the end of 2006, Swedish Nuclear Fuel and Waste Management Co (SKB) have presented a complete assessment of long-term safety for a KBS-3 repository. The SR-Can project demonstrates progress in SKB's capabilities in respect of the methodology for assessment of long-term safety in support of a licence application for a final repository. According to SKB's plans, applications to construct a geological repository will be submitted in 2009, supported by post-closure safety assessments. Project CLIMB (Catchment LInked Models of radiological effects in the Biosphere) was instituted in 2004 to provide SSI with an independent modelling capability when reviewing SKB's assessments. Modelling in CLIMB covers all aspects of performance assessment (PA) from nearfield releases to radiological consequences in the surface environment. This review of SR-Can provides the first opportunity to apply the models and to compare the CLIMB approach with developments at SKB. The aim of the independent calculations is to investigate key aspects of the PA models and so to better understand the assessment methodology used by SKB. Independent modelling allows critical review issues to be addressed by the application of alternative models and assumptions. Three reviews are undertaken here: - Reproduction of selected cases from SR-Can in order to demonstrate an adequate understanding of the PA model from details given in the SR-Can documentation. - Alternative conceptualisation of radionuclide transport and accumulation in the surface system. Two modelling approaches have been used: GEMA (the Generic Ecosystem Modelling Approach) is a traditional compartmental model similar to that used by SKB in SR-Can but with additional functionality and flexibility. The second approach takes continuous transport models to investigate contaminant migration through the Quaternary deposits into the surface drainage system. - The final strand of the CLIMB investigation

Radiological release analysis for the EFR project

International Nuclear Information System (INIS)

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

1996-01-01

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

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

International Nuclear Information System (INIS)

RITTMANN, P.D.

1999-01-01

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

Collaborative Radiological Response Planning

Science.gov (United States)

2013-12-01

DOE and EPA national laboratories .55 Additionally, the GAO conducted a survey of emergency management officials in cities, states and federal...for Biosecurity of UPMC, (2012). After fukushima: Managing the consequences of a radiological release. Retrieved from : http://issuu.com

Calculation notes that support accident scenario and consequence determination of a waste tank criticality

International Nuclear Information System (INIS)

Marusich, R.M. Westinghouse Hanford

1996-01-01

The purpose of this calculation note is to provide the basis for criticality consequences for the Tank Farm Safety Analysis Report (FSAR). Criticality scenario is developed and details and description of the analysis methods are provided

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

International Nuclear Information System (INIS)

Ustohalova, Veronika; Kueppers, Christian

2012-01-01

analytical solution of one- or two-dimensional dispersion-convention transport equation. The tool 'Migration' allows to quickly estimate the possible ranges of radioactive contamination in the ground water table over time whereas several parameters can be varied. The radiological exposure in the tool 'Exposure' can be calculated according to Gernrman approach AVV [3] or BglB [4]. The calculation model was tested on specific examples and the agreement with the reality was proven. There have been several approaches published on the subject of groundwater flow or radionuclide transfer in Asse mine but no one introduced more exactly radionuclide migration with coupled migration of decay chains and combined it in addition with the computation of radionuclide transfer in the biosphere. (authors)

Tank Bump Accident Potential and Consequences During Waste Retrieval

International Nuclear Information System (INIS)

BRATZEL, D.R.

2000-01-01

This report provides an evaluation of Hanford tank bump accident potential and consequences during waste retrieval operations. The purpose of this report is to consider the best available new information to support recommendations for safety controls. A new tank bump accident analysis for safe storage (Epstein et al. 2000) is extended for this purpose. A tank bump is a postulated event in which gases, consisting mostly of water vapor, are suddenly emitted from the waste and cause tank headspace pressurization. Tank bump scenarios, physical models, and frequency and consequence methods are fully described in Epstein et al. (2000). The analysis scope is waste retrieval from double-shell tanks (DSTs) including operation of equipment such as mixer pumps and air lift circulators. The analysis considers physical mechanisms for tank bump to formulate criteria for bump potential during retrieval, application of the criteria to the DSTs, evaluation of bump frequency, and consequence analysis of a bump. The result of the consequence analysis is the mass of waste released from tanks; radiological dose is calculated using standard methods (Cowley et al. 2000)

Dose calculations for severe LWR accident scenarios

International Nuclear Information System (INIS)

Margulies, T.S.; Martin, J.A. Jr.

1984-05-01

This report presents a set of precalculated doses based on a set of postulated accident releases and intended for use in emergency planning and emergency response. Doses were calculated for the PWR (Pressurized Water Reactor) accident categories of the Reactor Safety Study (WASH-1400) using the CRAC (Calculations of Reactor Accident Consequences) code. Whole body and thyroid doses are presented for a selected set of weather cases. For each weather case these calculations were performed for various times and distances including three different dose pathways - cloud (plume) shine, ground shine and inhalation. During an emergency this information can be useful since it is immediately available for projecting offsite radiological doses based on reactor accident sequence information in the absence of plant measurements of emission rates (source terms). It can be used for emergency drill scenario development as well

SHIELD 1.0: development of a shielding calculator program in diagnostic radiology; SHIELD 1.0: desenvolvimento de um programa de calculo de blindagem em radiodiagnostico

Energy Technology Data Exchange (ETDEWEB)

Santos, Romulo R.; Real, Jessica V.; Luz, Renata M. da [Hospital Sao Lucas (PUCRS), Porto Alegre, RS (Brazil); Friedrich, Barbara Q.; Silva, Ana Maria Marques da, E-mail: ana.marques@pucrs.br [Pontificia Universidade Catolica do Rio Grande do Sul (PUCRS), Porto Alegre, RS (Brazil)

2013-08-15

In shielding calculation of radiological facilities, several parameters are required, such as occupancy, use factor, number of patients, source-barrier distance, area type (controlled and uncontrolled), radiation (primary or secondary) and material used in the barrier. The shielding design optimization requires a review of several options about the physical facility design and, mainly, the achievement of the best cost-benefit relationship for the shielding material. To facilitate the development of this kind of design, a program to calculate the shielding in diagnostic radiology was implemented, based on data and limits established by National Council on Radiation Protection and Measurements (NCRP) 147 and SVS-MS 453/98. The program was developed in C⌗ language, and presents a graphical interface for user data input and reporting capabilities. The module initially implemented, called SHIELD 1.0, refers to calculating barriers for conventional X-ray rooms. The program validation was performed by the comparison with the results of examples of shielding calculations presented in NCRP 147.

White Paper: Curriculum in Interventional Radiology.

Science.gov (United States)

Mahnken, Andreas H; Bücker, Arno; Hohl, Christian; Berlis, Ansgar

2017-04-01

Purpose  Scope and clinical importance of interventional radiology markedly evolved over the last decades. Consequently it was acknowledged as independent subspecialty by the "European Union of Medical Specialists" (UEMS). Based on radiological imaging techniques Interventional Radiology is an integral part of Radiology. Materials und Methods  In 2009 the German Society for Interventional Radiology and minimally-invasive therapy (DeGIR) developed a structured training in Interventional Radiology. In cooperation with the German Society of Neuroradiology (DGNR) this training was extended to also cover Interventional Neuroradiology in 2012. Tailored for this training in Interventional Radiology a structured curriculum was developed, covering the scope of this modular training. Results  The curriculum is based on the DeGIR/DGNR modular training concept in Interventional Radiology. There is also an European Curriculum and Syllabus for Interventional Radiology developed by the "Cardiovascular and Interventional Radiological Society of Europe" (CIRSE). The presented curriculum in Interventional Radiology is designed to provide a uniform base for the training in Interventional Radiology in Germany, based on the competencies obtained during residency. Conclusion  This curriculum can be used as a basis for training in Interventional Radiology by all training sites. Key Points: · Interventional Radiology is an integral part of clinical radiology. · The German Society for Interventional Radiology and minimally-invasive therapy (DeGIR) developed a curriculum in Interventional Radiology. · This curriculum is an integrative basis for the training in interventional. Citation Format · Mahnken AH, Bücker A, Hohl C et al. White Paper: Curriculum in Interventional Radiology. Fortschr Röntgenstr 2017; 189: 309 - 311. © Georg Thieme Verlag KG Stuttgart · New York.

Radiology of congenital heart disease

International Nuclear Information System (INIS)

Amplatz, K.

1986-01-01

This is a text on the radiologic diagnosis of congenital heart disease and its clinical manifestations. The main thrust of the book is the logical approach which allows an understanding of the complex theory of congenital heart disease. The atlas gives a concise overview of the entire field of congenital heart disease. Emphasis is placed on the understanding of the pathophysiology and its clinical and radiological consequences. Surgical treatment is included since it provides a different viewpoint of the anatomy

Massive radiological releases profoundly differ from controlled releases

International Nuclear Information System (INIS)

Pascucci-Cahen, Ludivine; Patrick, Momal

2012-11-01

Preparing for a nuclear accident implies understanding potential consequences. While many specialized experts have been working on different particular aspects, surprisingly little effort has been dedicated to establishing the big picture and providing a global and balanced image of all major consequences. IRSN has been working on the cost of nuclear accidents, an exercise which must strive to be as comprehensive as possible since any omission obviously underestimates the cost. It therefore provides (ideally) an estimate of all cost components, thus revealing the structure of accident costs, and hence sketching a global picture. On a French PWR, it appears that controlled releases would cause an 'economical' accident with limited radiological consequences when compared to other costs; in contrast, massive releases would trigger a major crisis with strong radiological consequences. The two types of crises would confront managers with different types of challenges. (authors)

Accident consequence assessment code development

International Nuclear Information System (INIS)

Homma, T.; Togawa, O.

1991-01-01

This paper describes the new computer code system, OSCAAR developed for off-site consequence assessment of a potential nuclear accident. OSCAAR consists of several modules which have modeling capabilities in atmospheric transport, foodchain transport, dosimetry, emergency response and radiological health effects. The major modules of the consequence assessment code are described, highlighting the validation and verification of the models. (author)

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

International Nuclear Information System (INIS)

Margeanu, Sorin; Tatiana, Angelescu

2005-01-01

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

Derived reference levels for prenatal exposure in a radiological emergency

International Nuclear Information System (INIS)

Nuccetelli, C.; Risica, S.; Rogani, A.

2002-01-01

After the Chernobyl accident many countries renewed their radiological emergency plans, also considering the possibility of over boundary accidents. This has been set out by the 96/29/Euratom Directive (Council Directive, 1996), which states that E ach Member State shall ensure that account is taken of the fact that radiological emergencies may occur in connection with practices on or outside its territory and affect it . Moreover, after September 11, 2001, the need to prepare emergency plans for possible terroristic attacks became evident and these plans are now being worked out in many countries for intervention in case of biological, chemical and/or radiological risk. In the event of radiological emergency, all decisions to be taken are based on possible doses to critical groups (European Commission, 1997), which are the population groups most at risk. These critical groups are, in most cases, infants or children, given that dose coefficients for these age groups are generally higher than for adults. However, a new ICRP Recommendation (ICRP, 2001) has recently been published that gives dose coefficients for embryo/foetus due to intake by the mother, by inhalation or ingestion, of 31 radionuclides. Also as a result of the revaluation in the last years of the possible health effects of prenatal exposure to ionising radiation (see e.g. the review in P. Fattibene et al., 1999), the consequences for the embryo/foetus of a possible radiological emergency connected to a nuclear plant and to possible dispersion of Depleted Uranium (DU) in the environment are analysed and discussed in this paper. For the former type of accident, Derived Intervention Levels (DILs) are calculated for prenatal exposure due to acute inhalation by the mother (female member of the public) and an assessment is performed of ingestion doses for the offspring resulting from consumption of foodstuffs by the mother of which 10% of the annual consumption is contaminated at the maximum levels

Laboratory of environmental radiological surveillance

International Nuclear Information System (INIS)

Mendez G, A.; Marcial M, F.; Giber F, J.; Montiel R, E.; Leon del V, E.; Rivas C, I.; Leon G, M.V.; Lagunas G, E.; Aragon S, R.; Juarez N, A.; Alfaro L, M.M.

1991-12-01

The department of radiological protection of the ININ requests the collaboration of the Engineering Unit for the elaboration of the work project of the laboratory of environmental radiological surveillance. The emission of radioactive substances to the atmosphere like consequence of the normal operation of the Nuclear Center, constitutes an exhibition source from the man to the radiations that it should be appropriately watched over and controlled to be able to determine the population's potential exhibition that it lives in the area of influence of the installation. (Author)

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

International Nuclear Information System (INIS)

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

2007-05-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2007-05-15

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

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

Science.gov (United States)

2006-10-02

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

[Modern education in histopathology and radiology].

Science.gov (United States)

Maas, Mario; Mooi, Wolter J

2011-01-01

Radiological and pathological imaging constitute an essential part of modern medicine. Furthermore, by showing microscopic and radiological images many pathological processes can be made clearer and easier to understand. This has consequences for education. Many medical faculties are switching partly or entirely to the use of 'virtual microscopy', which amounts to studying digitalised histological preparations with the help of software that shows striking similarities to Google Earth. The requesting physician of the future will be able to make the most effective use of radiological tests when he or she has been trained in 'radiological thinking'. Students must realise that radiology depends not just on looking, as one might at holiday snaps, but more especially on interpreting what is seen. By using modern aids, it is possible to test the listeners' knowledge during lectures as a basis for the rest of the presentation. Collections of educational images are now widely available, including on the Internet.

Radiological Dispersion Devices: are we prepared?

Energy Technology Data Exchange (ETDEWEB)

Sohier, Alain [Decision Strategy Research Department (Radiation Protection Division), Belgian Nuclear Research Centre (SCK-CEN), Boeretang 200, B-2400 Mol (Belgium)]. E-mail: asohier@sckcen.be; Hardeman, Frank [Decision Strategy Research Department (Radiation Protection Division), Belgian Nuclear Research Centre (SCK-CEN), Boeretang 200, B-2400 Mol (Belgium)

2006-07-01

Already before the events of September 11th 2001 concern was raised about the spread of orphan sources and their potential use in Radiological Dispersion Devices by terrorist groups. Although most of the simulated scenarios foresee a rather limited direct health impact on the population, the affected region would suffer from the indirect consequences such as social disruption, cleanup requirements and economic costs. The nature of such a radiological attack would anyway be different compared to conventional radiological accidents, basically because it can happen anywhere at any time. Part of the response resides in a general preparedness scheme incorporating attacks with Radiological Dispersion Devices. Training of different potential intervention teams is essential. The response would consist of a prioritised list of actions adapted to the circumstances. As the psychosocial dimension of the crisis could be worse than the purely radiological one, an adapted communication strategy with the public aspect would be a key issue.

Radiological Dispersion Devices: are we prepared?

International Nuclear Information System (INIS)

Sohier, Alain; Hardeman, Frank

2006-01-01

Already before the events of September 11th 2001 concern was raised about the spread of orphan sources and their potential use in Radiological Dispersion Devices by terrorist groups. Although most of the simulated scenarios foresee a rather limited direct health impact on the population, the affected region would suffer from the indirect consequences such as social disruption, cleanup requirements and economic costs. The nature of such a radiological attack would anyway be different compared to conventional radiological accidents, basically because it can happen anywhere at any time. Part of the response resides in a general preparedness scheme incorporating attacks with Radiological Dispersion Devices. Training of different potential intervention teams is essential. The response would consist of a prioritised list of actions adapted to the circumstances. As the psychosocial dimension of the crisis could be worse than the purely radiological one, an adapted communication strategy with the public aspect would be a key issue

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

International Nuclear Information System (INIS)

2015-08-01

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

Physical correlates of radiologic heart volume

International Nuclear Information System (INIS)

Christie, D.

1978-01-01

Radiologic heart volume was calculated on a 10 per cent random sample of subjects examined in the London Civil Service Health Survey. Data were available for 1 188 men over the age of 40, and the importance of correcting radiologic heart volume for body size, age and heart rate was demonstrated. After these variables were taken into account, the most important association found was with blood pressure. Radiologic heart volume has potential value in cardiovascular screening programmes. (Auth.)

Evaluation means of the consequences on the environment of an accidental situation

International Nuclear Information System (INIS)

Crabol, B.

1989-04-01

The Safety and Nuclear Protection Institute (SNPI) available means to the management of a nuclear accident, especially the Crisis Technical Center (CTC), are presented. The CTC is able to supply the needs during the ''threatening'' phase, as well as in the after-accident phase. In order to evaluate the radiological consequences and to give advise, the work of experts is asked, during the different phases of the accident. The CTC is responsible for the data base, for the data acquisition, interpretation and exchange. They are able to perform calculations concerning the environmental pollution transfer [fr

Radiological monitoring of food in Cuba

International Nuclear Information System (INIS)

Jerez V, S.F.

1996-01-01

The appearing of the problem for protecting the environment from radioactive contamination is not an accidental matter. The introduction into the earth crust of radioactive material coming from nuclear weapons, accidents, wastes, etc, has caused, as a consequence, the contamination of the biosphere. The extensive trade of food in our country has made necessary the establishment of radiological monitoring in food, which was organized by the Department of Public Health. The structure, functions, characteristics and aspects related to radiological monitoring of food in Cuba are shown in the present paper. The organization and resources for performing the monitoring program, both for normal conditions and for nuclear and/or radiological emergency cases, are detailed. (author). 12 refs., 2 figs

What constitutes a radiology radiation accident

International Nuclear Information System (INIS)

Wallace, A.; Edmonds, K.; Hayton, A.; Tingey, D.

2010-01-01

Full text: A review of the literature indicates a very small number of articles on radiology radiation accidents. This may be due to there being no agreed definition of the term 'accident' when applied to radiology incidents. As the intensity of X-ray beams and the functionality of various modalities increase there is a consequent development in procedures to which 'high dose' applications are required. We may therefore expect to see more incidents in future. How are we to manage them? Radiology radiation accidents are usually exemplified by deterministic skin burns which may take many weeks or months to become apparent and any procedure leading to a radiation induced fatality is difficult to prove. (author)

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

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

International Nuclear Information System (INIS)

Nasvit, O.

1998-01-01

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

History of metaphoric signs in radiology

Energy Technology Data Exchange (ETDEWEB)

Baker, Stephen R., E-mail: bakersr@umdnj.edu; Noorelahi, Yasser M., E-mail: dr.ynoorelahi@gmail.com; Ghosh, Shanchita, E-mail: Ghoshs1@umdnj.edu; Yang, Lily C., E-mail: yangclily@gmail.com; Kasper, David J., E-mail: dkasp86@gmail.com

2013-09-15

Purpose: To survey the nearly 100 year history of metaphoric sign naming in radiology describing the pace of their overall accumulation in the radiology canon, their specific rates of growth by modality and subspecialty and the characteristics of the referents to which the signs are attached. Materials and methods: A comprehensive list of metaphoric signs was compiled from a search of articles in several major English language radiology journals, from a roster compiled in a monograph on the subject published in 1984 and from a search of several databases to find signs published in the first half of the 20th century. Results: The growth of radiological metaphorical signs naming was slow for several decades after the first one was published in 1918. It then increased rapidly until the 1980s encompassing all modalities and subspecialties. Recently the practice has shown a marked and steady decline. Conclusion: Metaphoric sign naming was a frequently reported contribution to the radiological literature in the second half of the 20th century corresponding with Radiology's growth as a descriptive discipline. Its decline since then may be a consequence of Radiology's evolution into a more analytic, data-driven field of inquiry.

History of metaphoric signs in radiology

International Nuclear Information System (INIS)

Baker, Stephen R.; Noorelahi, Yasser M.; Ghosh, Shanchita; Yang, Lily C.; Kasper, David J.

2013-01-01

Purpose: To survey the nearly 100 year history of metaphoric sign naming in radiology describing the pace of their overall accumulation in the radiology canon, their specific rates of growth by modality and subspecialty and the characteristics of the referents to which the signs are attached. Materials and methods: A comprehensive list of metaphoric signs was compiled from a search of articles in several major English language radiology journals, from a roster compiled in a monograph on the subject published in 1984 and from a search of several databases to find signs published in the first half of the 20th century. Results: The growth of radiological metaphorical signs naming was slow for several decades after the first one was published in 1918. It then increased rapidly until the 1980s encompassing all modalities and subspecialties. Recently the practice has shown a marked and steady decline. Conclusion: Metaphoric sign naming was a frequently reported contribution to the radiological literature in the second half of the 20th century corresponding with Radiology's growth as a descriptive discipline. Its decline since then may be a consequence of Radiology's evolution into a more analytic, data-driven field of inquiry

Calculation notes that support accident scenario and consequence of the in-tank fuel fire/deflageration

International Nuclear Information System (INIS)

Crowe, R.D. Westinghouse Hanford

1996-01-01

The purpose of this calculation note is to provide the basis for In-Tank Fuel fire/Deflageration consequence for the Tank Farm Safety Analysis Report (FSAR). Tank Fuel Fire/Deflageration scenario is developed and details and description of the analysis methods are provided

Calculation notes that support accident scenario and consequence of the in-tank fuel fire/deflagration

Energy Technology Data Exchange (ETDEWEB)

Crowe, R.D.

1996-09-27

The purpose of this calculation note is to provide the basis for In-Tank Fuel Fire/Deflageration consequence for the Tank Farm Safety Analysis Report (FSAR). Tank Fuel Fire/Deflageration scenario is developed and details and description of the analysis methods are provided.

SSI's independent consequence calculations in support of the regulatory review of the SR-Can safety assessment

Energy Technology Data Exchange (ETDEWEB)

Shulan Xu; Dverstorp, Bjoern (Swedish Radiation Protection Authority, Stockholm (Sweden)); Woerman, Anders; Marklund, Lars (Royal Institute of Technology (KTH), Stockholm (SE)); Klos, Richard (Aleksandria Sciences, Sheffield (GB)); Shaw, George (Univ. of Nottingham (GB))

2008-03-15

With the publication of the SR-Can report at the end of 2006, Swedish Nuclear Fuel and Waste Management Co (SKB) have presented a complete assessment of long-term safety for a KBS-3 repository. The SR-Can project demonstrates progress in SKB's capabilities in respect of the methodology for assessment of long-term safety in support of a licence application for a final repository. According to SKB's plans, applications to construct a geological repository will be submitted in 2009, supported by post-closure safety assessments. Project CLIMB (Catchment LInked Models of radiological effects in the Biosphere) was instituted in 2004 to provide SSI with an independent modelling capability when reviewing SKB's assessments. Modelling in CLIMB covers all aspects of performance assessment (PA) from nearfield releases to radiological consequences in the surface environment. This review of SR-Can provides the first opportunity to apply the models and to compare the CLIMB approach with developments at SKB. The aim of the independent calculations is to investigate key aspects of the PA models and so to better understand the assessment methodology used by SKB. Independent modelling allows critical review issues to be addressed by the application of alternative models and assumptions. Three reviews are undertaken here: - Reproduction of selected cases from SR-Can in order to demonstrate an adequate understanding of the PA model from details given in the SR-Can documentation. - Alternative conceptualisation of radionuclide transport and accumulation in the surface system. Two modelling approaches have been used: GEMA (the Generic Ecosystem Modelling Approach) is a traditional compartmental model similar to that used by SKB in SR-Can but with additional functionality and flexibility. The second approach takes continuous transport models to investigate contaminant migration through the Quaternary deposits into the surface drainage system. - The final strand of the CLIMB

Parameter calculation tool for the application of radiological dose projection codes; Herramienta de calculo de parametros para la aplicacion de codigos de proyeccion de dosis radiologicas

Energy Technology Data Exchange (ETDEWEB)

Galindo G, I. F.; Vergara del C, J. A.; Galvan A, S. J. [Instituto Nacional de Electricidad y Energias Limpias, Reforma 113, Col. Palmira, 62490 Cuernavaca, Morelos (Mexico); Tijerina S, F., E-mail: francisco.tijerina@cfe.gob.mx [CFE, Central Nucleoelectrica Laguna Verde, Carretera Federal Cardel-Nautla Km 42.5, 91476 Municipio Alto Lucero, Veracruz (Mexico)

2016-09-15

The use of specialized codes to estimate the radiation dose projection to an emergency postulated event at a nuclear power plant requires that certain plant data be available according to the event being simulated. The calculation of the possible radiological release is the critical activity to carry out the emergency actions. However, not all of the plant data required are obtained directly from the plant but need to be calculated. In this paper we present a computational tool that calculates the plant data required to use the radiological dose estimation codes. The tool provides the required information when there is a gas emergency venting event in the primary containment atmosphere, whether well or dry well and also calculates the time in which the spent fuel pool would be discovered in the event of a leak of water on some of the walls or floor of the pool. The tool developed has mathematical models for the processes involved such as: compressible flow in pipes considering area change and for constant area, taking into account the effects of friction and for the case of the spent fuel pool hydraulic models to calculate the time in which a container is emptied. The models implemented in the tool are validated with data from the literature for simulated cases. The results with the tool are very similar to those of reference. This tool will also be very supportive so that in postulated emergency cases can use the radiological dose estimation codes to adequately and efficiently determine the actions to be taken in a way that affects as little as possible. (Author)

A kinematic-based methodology for radiological protection: Runoff analysis to calculate the effective dose for internal exposure caused by ingestion of radioactive isotopes

Science.gov (United States)

Sasaki, Syota; Yamada, Tadashi; Yamada, Tomohito J.

2014-05-01

We aim to propose a kinematic-based methodology similar with runoff analysis for readily understandable radiological protection. A merit of this methodology is to produce sufficiently accurate effective doses by basic analysis. The great earthquake attacked the north-east area in Japan on March 11, 2011. The system of electrical facilities to control Fukushima Daiichi nuclear power plant was completely destroyed by the following tsunamis. From the damaged reactor containment vessels, an amount of radioactive isotopes had leaked and been diffused in the vicinity of the plant. Radiological internal exposure caused by ingestion of food containing radioactive isotopes has become an issue of great interest to the public, and has caused excessive anxiety because of a deficiency of fundamental knowledge concerning radioactivity. Concentrations of radioactivity in the human body and internal exposure have been studied extensively. Previous radiologic studies, for example, studies by International Commission on Radiological Protection(ICRP), employ a large-scale computational simulation including actual mechanism of metabolism in the human body. While computational simulation is a standard method for calculating exposure doses among radiology specialists, these methods, although exact, are too difficult for non-specialists to grasp the whole image owing to the sophistication. In this study, the human body is treated as a vessel. The number of radioactive atoms in the human body can be described by an equation of continuity, which is the only governing equation. Half-life, the period of time required for the amount of a substance decreases by half, is only parameter to calculate the number of radioactive isotopes in the human body. Half-life depends only on the kinds of nuclides, there are no arbitrary parameters. It is known that the number of radioactive isotopes decrease exponentially by radioactive decay (physical outflow). It is also known that radioactive isotopes

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

Consequences of radioactive deposition on aquatic environments

International Nuclear Information System (INIS)

Suolanen, V.

1994-12-01

The publication concentrates on the analyses of the main effects of radioactive deposition on Nordic aquatic environments. A modelling approach is applied for predicting the temporal behaviour of concentrations in fish of inland freshwater ecosystems. The observed values are considered in parallel with the calculations. The time-integrated consequences, the radiation doses are estimated for the relatively significant dose pathways. After a preliminary study of various lake environments in Nordic countries, three representative examples of lake systems were selected for closer consideration: small forest lake, medium-sized forest lake and mountain lake. The effects of changes in the trophic levels of lakes are also tentatively accounted for. The results of the analyses indicate that the radiological consequences of shallow forest lakes are greater than those of mountain lakes which usually have shorter turnover times compared to forest lakes. In long-term consideration, the fish ingestion pathway may in general become important and, in addition to the external exposure, has a high contribution to the expected doses. (orig.) (8 refs., 11 figs., 9 tabs.)

Model description. NUDOS: A computer program for assessing the consequences of airborne releases of radionuclides

International Nuclear Information System (INIS)

Poley, A.D.

1996-02-01

NUDOS is a computer program that can be used to evaluate the consequences of airborne releases of radioactive material. The consequences which can be evaluated are individual dose and associated radiological risk, collective dose and the contamination of land. The code is capable of dealing with both continuous (routine) and accidental releases. For accidental releases both deterministic and probabilistic calculations can be performed, and the impact and effectiveness of emergency actions can be evaluated. This report contains a description of the models contained in NUDOS92 and the recommended values for the input parameters of these models. Additionally, a short overview is given of the future model improvement planned for the next NUDOS-version. (orig.)

Stochastic Consequence Analysis for Waste Leaks

International Nuclear Information System (INIS)

HEY, B.E.

2000-01-01

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

[Legal aspects of post-mortem radiology in the Netherlands].

Science.gov (United States)

Venderink, W; Dute, J C J

2016-01-01

In the Netherlands, the application of post-mortem radiology (virtual autopsy) is on the rise. Contrary to conventional autopsy, with post-mortem radiology the body remains intact. There is uncertainty concerning the legal admissibility of post-mortem radiology, since the Dutch Corpse Disposal Act does not contain any specific regulations for this technique. Autopsy and post-mortem radiology differ significantly from a technical aspect, but these differences do not have far-reaching legal consequences from a legal perspective. Even though the body remains intact during post-mortem radiology, the bodily integrity of a deceased person is breached if it would be applied without previously obtained consent. This permission can only be obtained after the relatives are fully informed about the proposed activity. In this respect, it is not relevant which technique is used, be it post-mortem radiology or autopsy. Therefore, the other legal conditions for post-mortem radiology are essentially identical to those for autopsy.

77 FR 5281 - State-of-the-Art Reactor Consequence Analyses Reports

Science.gov (United States)

2012-02-02

... NUCLEAR REGULATORY COMMISSION [Docket ID: NRC-2012-0022] State-of-the-Art Reactor Consequence... release of Draft NUREG-1935, ``State-of-the-Art Reactor Consequence Analyses (SOARCA) Report,'' for public... offsite radiological health consequences for potential severe reactor accidents for the Peach Bottom...

The Radiological Accident in Lia, Georgia

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-12-15

The use of radioactive material offers a wide range of benefits to medicine, research and industry throughout the world. Precautions are necessary, however, to limit the exposure of people to the radiation emitted. Where the amount of radioactive material is substantial, as in the case of radiotherapy or industrial radiography sources, great care is required to prevent accidents which could have severe consequences. Nevertheless, in spite of the precautions taken, serious accidents involving radiation sources continue to occur, albeit infrequently. The IAEA conducts follow-up reviews of such serious accidents to provide an account of their circumstances and consequences, from which organizations with responsibilities for radiation protection, safety of sources and emergency preparedness and response may learn. A serious radiological accident occurred in Georgia on 2 December 2001, when three inhabitants of the village of Lia found two metal objects in the forest while collecting firewood. These objects were {sup 90}Sr sources with an activity of 1295 TBq. The three inhabitants used the objects as heaters when spending the night in the forest. The major cause of the accident was the improper and unauthorized abandonment of radiation sources in Georgia and the absence of clear labels or radiation signs on the sources warning of the potential radiation hazard. Under the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (Assistance Convention), the Georgian authorities requested assistance from the IAEA to advise on the dose assessment, source recovery and medical management of those involved in the accident. This publication describes the circumstances and events surrounding the accident, its management and the medical treatment of the people exposed. It also describes the dose reconstruction calculations and biodosimetry assessments conducted. A number of uncertainties remain relating to some details of the accident. However

The Radiological Accident in Lia, Georgia

International Nuclear Information System (INIS)

2014-12-01

The use of radioactive material offers a wide range of benefits to medicine, research and industry throughout the world. Precautions are necessary, however, to limit the exposure of people to the radiation emitted. Where the amount of radioactive material is substantial, as in the case of radiotherapy or industrial radiography sources, great care is required to prevent accidents which could have severe consequences. Nevertheless, in spite of the precautions taken, serious accidents involving radiation sources continue to occur, albeit infrequently. The IAEA conducts follow-up reviews of such serious accidents to provide an account of their circumstances and consequences, from which organizations with responsibilities for radiation protection, safety of sources and emergency preparedness and response may learn. A serious radiological accident occurred in Georgia on 2 December 2001, when three inhabitants of the village of Lia found two metal objects in the forest while collecting firewood. These objects were 90 Sr sources with an activity of 1295 TBq. The three inhabitants used the objects as heaters when spending the night in the forest. The major cause of the accident was the improper and unauthorized abandonment of radiation sources in Georgia and the absence of clear labels or radiation signs on the sources warning of the potential radiation hazard. Under the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (Assistance Convention), the Georgian authorities requested assistance from the IAEA to advise on the dose assessment, source recovery and medical management of those involved in the accident. This publication describes the circumstances and events surrounding the accident, its management and the medical treatment of the people exposed. It also describes the dose reconstruction calculations and biodosimetry assessments conducted. A number of uncertainties remain relating to some details of the accident. However, sufficient

The radiological accident in Yanango

International Nuclear Information System (INIS)

2000-01-01

The use of nuclear technologies has fostered new, more effective and efficient medical procedures and has substantially improved diagnostic and therapeutic capabilities. However, in order that the benefits of the use of ionizing radiation outweigh the potential hazards posed by this medium, it is important that radiation protection and safety standards be established to govern every aspect of the application of ionizing radiation. Adherence to these standards needs to be maintained through effective regulatory control, safe operational procedures and a safety culture that is shared by all. Occasionally, established safety procedures are violated and serious radiological consequences ensue. The radiological accident described in this report, which took place in Lilo, Georgia, was a result of such an infraction. Sealed radiation sources had been abandoned by a previous owner at a site without following established regulatory safety procedures, for example by transferring the sources to the new owner or treating them as spent material and conditioning them as waste. As a consequence, 11 individuals at the site were exposed for a long period of time to high doses of radiation which resulted inter alia in severe radiation induced skin injuries. Although at the time of the accident Georgia was not an IAEA Member State and was not a signatory of the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency, the IAEA still provided assistance to the Government of Georgia in assessing the radiological situation, while the World Health Organization (WHO) assisted in alleviating the medical consequences of the accident. The two organizations co-operated closely from the beginning, following the request for assistance by the Georgian Government. The IAEA conducted the radiological assessment and was responsible for preparing the report. The WHO and its collaborating centres within the Radiation Emergency Medical Preparedness and Assistance Network

Workplace Bullying in Radiology and Radiation Oncology.

Science.gov (United States)

Parikh, Jay R; Harolds, Jay A; Bluth, Edward I

2017-08-01

Workplace bullying is common in health care and has recently been reported in both radiology and radiation oncology. The purpose of this article is to increase awareness of bullying and its potential consequences in radiology and radiation oncology. Bullying behavior may involve abuse, humiliation, intimidation, or insults; is usually repetitive; and causes distress in victims. Workplace bullying is more common in health care than in other industries. Surveys of radiation therapists in the United States, student radiographers in England, and physicians-in-training showed that substantial proportions of respondents had been subjected to workplace bullying. No studies were found that addressed workplace bullying specifically in diagnostic radiology or radiation oncology residents. Potential consequences of workplace bullying in health care include anxiety, depression, and health problems in victims; harm to patients as a result of victims' reduced ability to concentrate; and reduced morale and high turnover in the workplace. The Joint Commission has established leadership standards addressing inappropriate behavior, including bullying, in the workplace. The ACR Commission on Human Resources recommends that organizations take steps to prevent bullying. Those steps include education, including education to ensure that the line between the Socratic method and bullying is not crossed, and the establishment of policies to facilitate reporting of bullying and support victims of bullying. Copyright © 2016 American College of Radiology. Published by Elsevier Inc. All rights reserved.

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

Energy Technology Data Exchange (ETDEWEB)

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

2003-01-01

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

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

International Nuclear Information System (INIS)

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

1992-06-01

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

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

Science.gov (United States)

den Heeten, G J; Barneveld Binkhuysen, F H

2001-08-25

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

Preventive Rad/Nuc Detection Equipment Categorization for Consequence Management

Energy Technology Data Exchange (ETDEWEB)

Buddemeier, B. R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Musolino, S. V. [Brookhaven National Lab. (BNL), Upton, NY (United States); Klemic, G. [US Dept. of Homeland Security National Security Technology Lab., New York, NY (United States)

2017-06-01

The overall objective of this project is to research, evaluate, and test first responder preventive radiological/nuclear detection equipment (PRND) to provide state and local agencies with guidance on how to best use this equipment for response after a radiological/nuclear release or detonation. While the equipment being tested in this effort has been specifically designed for detection and interdiction operations, the fleet of PRND equipment can help fill critical needs for radiological instrumentation should a consequence management response take place. This effort will provide scientific guidance on the best way to deploy and operate this class of equipment for consequence management missions. With the support of the US Department of Homeland Security’s (DHS) Domestic Nuclear Detection Office (DNDO), PRND equipment has been placed into service at federal, state, and local agencies throughout the nation. If the equipment capability and limitations are taken into account, this large inventory can be repurposed to support the emergency response in the aftermath of a radiological of nuclear event. This report evaluates PRND equipment to define key categories of equipment and the types of missions they can be used for. This is important because there are over 100 different types of PRND equipment, often with significantly different capabilities with respect to the consequence management mission. The current DNDO draft NIMS PRND equipment types were used as a foundation and expanded, when necessary, to address key characteristics important for the consequence mission. Table 1 provides a summary of the PRND instrument categories developed for this effort. Also included on the table are some common response mission detection equipment categories that will be used for capability comparisons.

Cosyma a new programme package for accident consequence assessment

International Nuclear Information System (INIS)

Kelly, G.N.

1991-01-01

This report gives details of a new programme package for accident consequence assessment, prepared under the CEC's Maria programme (Methods for assessing the radiological impact of accidents) initiated in 1982 to review and build on the nuclear accident consequence assessment methods in use within the European Community

Proposed method to calculate FRMAC intervention levels for the assessment of radiologically contaminated food and comparison of the proposed method to the U.S. FDA's method to calculate derived intervention levels

Energy Technology Data Exchange (ETDEWEB)

Kraus, Terrence D.; Hunt, Brian D.

2014-02-01

This report reviews the method recommended by the U.S. Food and Drug Administration for calculating Derived Intervention Levels (DILs) and identifies potential improvements to the DIL calculation method to support more accurate ingestion pathway analyses and protective action decisions. Further, this report proposes an alternate method for use by the Federal Emergency Radiological Assessment Center (FRMAC) to calculate FRMAC Intervention Levels (FILs). The default approach of the FRMAC during an emergency response is to use the FDA recommended methods. However, FRMAC recommends implementing the FIL method because we believe it to be more technically accurate. FRMAC will only implement the FIL method when approved by the FDA representative on the Federal Advisory Team for Environment, Food, and Health.

Radiological NESHAP ANNUAL REPORT CY 2016.

Energy Technology Data Exchange (ETDEWEB)

Evelo, Stacie [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2017-06-01

This report provides a summary of the radionuclide releases from the United States (U.S.) Department of Energy (DOE) National Nuclear Security Administration facilities at Sandia National Laboratories, New Mexico (SNL/NM) during Calendar Year (CY) 2016, including the data, calculations, and supporting documentation for demonstrating compliance with 40 Code of Federal Regulation (CFR) 61, Subpart H--NATIONAL EMISSION STANDARDS FOR EMISSIONS OF RADIONUCLIDES OTHER THAN RADON FROM DEPARTMENT OF ENERGY FACILITIES (Radiological NESHAP). A description is given of the sources and their contributions to the overall dose assessment. In addition, the maximally exposed individual (MEI) radiological dose calculation and the population dose to local and regional residents are discussed.

Offsite radiological consequence analysis for the bounding aircraft crash accident

International Nuclear Information System (INIS)

OBERG, B.D.

2003-01-01

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

Validation of Dose Calculation Codes for Clearance

International Nuclear Information System (INIS)

Menon, S.; Wirendal, B.; Bjerler, J.; Studsvik; Teunckens, L.

2003-01-01

Various international and national bodies such as the International Atomic Energy Agency, the European Commission, the US Nuclear Regulatory Commission have put forward proposals or guidance documents to regulate the ''clearance'' from regulatory control of very low level radioactive material, in order to allow its recycling as a material management practice. All these proposals are based on predicted scenarios for subsequent utilization of the released materials. The calculation models used in these scenarios tend to utilize conservative data regarding exposure times and dose uptake as well as other assumptions as a safeguard against uncertainties. None of these models has ever been validated by comparison with the actual real life practice of recycling. An international project was organized in order to validate some of the assumptions made in these calculation models, and, thereby, better assess the radiological consequences of recycling on a practical large scale

A study on the weather sampling method for probabilistic consequence analysis

International Nuclear Information System (INIS)

Oh, Hae Cheol

1996-02-01

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

Safety aspects in radiology

International Nuclear Information System (INIS)

Silva, D.C. da.

1991-05-01

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

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

New threats and new challenges for radiological decision support

DEFF Research Database (Denmark)

Andersson, Kasper Grann; Astrup, Poul; Mikkelsen, Torben

2011-01-01

It is described how ongoing work will extend European standard decision support systems currently integrated in the nuclear power plant preparedness in many countries, to enable estimation of the radiological consequences of atmospheric dispersion of contaminants following a terror attack in a city....... Factors relating to the contaminant release processes, dispersion, deposition and post deposition migration are discussed, and non-radiological issues are highlighted in relation to decision making....

How the radiological accident of Goiania was initially determined

International Nuclear Information System (INIS)

Ferreira, W.M.

2000-01-01

Mainly the initial actions adopted to minimise the consequences of radiological accident involving the public are very important for bringing the situation to the normality. In this work the author presents a short history about the radiological accident with a 137 Cs source occurred in the city of Goiania, Brazil in 1987 as well as the actions adopted by him during the first hours after the detection of the accident. (author)

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)

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

International Nuclear Information System (INIS)

Imanaka, Tetsuji; Koide, Hiroaki; Kobayashi, Keiji

1998-01-01

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

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

International Nuclear Information System (INIS)

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

2004-01-01

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

Plan gauge in pediatric radiology: dosimetry (experience of ten months)

International Nuclear Information System (INIS)

Fraysse, V.; Lacaze, M.T.; Ferran, J.L.; Couture, A.; Gardien, E.

2006-01-01

The objectives were to optimize the radiological constants in the use of the sensors plans(shots) in general radiology. Definition of doses, calculation and communication to the parents of the received dose. (N.C.)

Radiological and radioisotope diagnosis of pericarditides in lymphogranulomatosis

Energy Technology Data Exchange (ETDEWEB)

Astanov, B M; Kuz' min, V P; Shapiro, I B; Romagin, V K [Nauchno-Issledovatel' skij Inst. Meditsinskoj Radiologii, Obninsk (USSR)

1980-04-01

The radiological and scintigraphic results of 52 patients suffering from granulomatosis and pericarditis, the latter as a consequence of radiotherapy in 30 cases, were compared. The radiological examination after application of an artificial pneumopericardium allows the interpretation of both the quantity of the exudate and the condition of epicardium and pericardium. Applying additional scintigraphic methods central hemodynamic parameter can be examined; thus in exsudative pericarditis s decrease of the cardiac output and of the cardiac index could be stated intensifying with increasing exsudation.

Image Quality in Vascular Radiology

International Nuclear Information System (INIS)

Vanhavere, F.; Struelens, L.

2005-01-01

In vascular radiology, the radiologists use the radiological image to diagnose or treat a specific vascular structure. From literature, we know that related doses are high and that large dose variability exists between different hospitals. The application of the optimization principle is therefore necessary and is obliged by the new legislation. So far, very little fieldwork has been performed and no practical instructions are available to do the necessary work. It's indisputable that obtaining quantitative data is of great interest for optimization purposes. In order to gain insight into these doses and the possible measures for dose reduction, we performed a comparative study in 7 hospitals. Patient doses will be measured and calculated for specific procedures in vascular radiology and evaluated against their most influencing parameters. In view of optimization purposes, a protocol for dose audit will be set-up. From the results and conclusions in this study, experimentally based guidelines will be proposed, in order to improve clinical practice in vascular radiology

An investigation of entrance surface dose calculations for diagnostic radiology using Monte Carlo simulations and radiotherapy dosimetry formalisms

International Nuclear Information System (INIS)

Omrane, L Ben; Verhaegen, F; Chahed, N; Mtimet, S

2003-01-01

Our aim in this work was to investigate the methodology used in the determination of the entrance surface dose (ESD) in diagnostic radiology. In kV x-rays for low-energy photons (tube potential up to 160 kV, HVL: 1-8 mm Al), the ESD is based on the use of the ratio of mass-energy absorption coefficients and backscatter factors. A full simulation of the photon and electron transport in a kilovoltage x-ray unit, using the Monte Carlo code BEAM/EGS4, was performed to obtain an accurate beam phase space for use in dose calculation. The modelled phase space was experimentally validated for the beam qualities (measured HVL: 3.3 mm Al-2.2 mm Cu) and showed good agreement between calculated and measured HVLs, air kerma and relative dose distributions. We have computed the conversion factors from air kerma to water or soft tissue absorbed dose at the surface of a phantom for beam qualities (HVL: 3.3-8.35 mm Al). The same model was also used to calculate the ESD in water and in soft tissue for the low-energy photon range considered. The results show that the numerical differences between the air kerma and the water kerma based backscatter factors are insignificant. The same conclusion was reached for the (μ en /ρ) ratios, for soft tissue to air, evaluated using either the primary photon spectra or the spectra at the surface of a phantom. Furthermore, the good agreement obtained for the computation of the conversion factors with a full BEAM/EGS4 model confirms the previous studies which are based on different sources for the spectral distribution and different beam geometries (pencil beam or point source assumptions). On the other hand, the ESD in water or soft tissue is well described either with the B air or the B w formalism. Conversion factors from air kerma to ESD in these media are proposed in this work for several beam qualities in diagnostic radiology

A simplified model for calculating early offsite consequences from nuclear reactor accidents

International Nuclear Information System (INIS)

Madni, I.K.; Cazzoli, E.G.; Khatib-Rahbar, M.

1988-07-01

A personal computer-based model, SMART, has been developed that uses an integral approach for calculating early offsite consequences from nuclear reactor accidents. The solution procedure uses simplified meteorology and involves direct analytic integration of air concentration equations over time and position. This is different from the discretization approach currently used in the CRAC2 and MACCS codes. The SMART code is fast-running, thereby providing a valuable tool for sensitivity and uncertainty studies. The code was benchmarked against both MACCS version 1.4 and CRAC2. Results of benchmarking and detailed sensitivity/uncertainty analyses using SMART are presented. 34 refs., 21 figs., 24 tabs

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

International Nuclear Information System (INIS)

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

1985-08-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1985-08-01

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

Calculations of reactor-accident consequences, Version 2. CRAC2: computer code user's guide

International Nuclear Information System (INIS)

Ritchie, L.T.; Johnson, J.D.; Blond, R.M.

1983-02-01

The CRAC2 computer code is a revision of the Calculation of Reactor Accident Consequences computer code, CRAC, developed for the Reactor Safety Study. The CRAC2 computer code incorporates significant modeling improvements in the areas of weather sequence sampling and emergency response, and refinements to the plume rise, atmospheric dispersion, and wet deposition models. New output capabilities have also been added. This guide is to facilitate the informed and intelligent use of CRAC2. It includes descriptions of the input data, the output results, the file structures, control information, and five sample problems

Comparison of MACCS users calculations for the international comparison exercise on probabilistic accident consequence assessment code, October 1989--June 1993

International Nuclear Information System (INIS)

Neymotin, L.

1994-04-01

Over the past several years, the OECD/NEA and CEC sponsored an international program intercomparing a group of six probabilistic consequence assessment (PCA) codes designed to simulate health and economic consequences of radioactive releases into atmosphere of radioactive materials following severe accidents at nuclear power plants (NPPs): ARANO (Finland), CONDOR (UK), COSYMA (CEC), LENA (Sweden), MACCS (USA), and OSCAAR (Japan). In parallel with this effort, two separate groups performed similar calculations using the MACCS and COSYMA codes. Results produced in the MACCS Users Group (Greece, Italy, Spain, and USA) calculations and their comparison are contained in the present report. Version 1.5.11.1 of the MACCS code was used for the calculations. Good agreement between the results produced in the four participating calculations has been reached, with the exception of the results related to the ingestion pathway dose predictions. The main reason for the scatter in those particular results is attributed to the lack of a straightforward implementation of the specifications for agricultural production and counter-measures criteria provided for the exercise. A significantly smaller scatter in predictions of other consequences was successfully explained by differences in meteorological files and weather sampling, grids, rain distance intervals, dispersion model options, and population distributions

Educational treasures in Radiology: The Radiology Olympics - striving for gold in Radiology education

OpenAIRE

Talanow, Roland

2010-01-01

This article focuses on Radiology Olympics (www.RadiologyOlympics.com) - a collaboration with the international Radiology community for Radiology education, Radiolopolis (www.Radiolopolis.com). The Radiology Olympics honour the movers and shakers in Radiology education and offer an easy to use platform for educating medical professionals based on Radiology cases.

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

Critical review of the reactor-safety study radiological health effects model. Final report

Energy Technology Data Exchange (ETDEWEB)

Cooper, D.W.; Evans, J.S.; Jacob, N.; Kase, K.R.; Maletskos, C.J.; Robertson, J.B.; Smith, D.G.

1983-03-01

This review of the radiological health effects models originally presented in the Reactor Safety Study (RSS) and currently used by the US Nuclear Regulatory Commission (NRC) was undertaken to assist the NRC in determining whether or not to revise the models and to aid in the revision, if undertaken. The models as presented in the RSS and as implemented in the CRAC (Calculations of Reactor Accident Consequences) Code are described and critiqued. The major elements analyzed are those concerning dosimetry, early effects, and late effects. The published comments on the models are summarized, as are the important findings since the publication of the RSS.

Critical review of the reactor-safety study radiological health effects model. Final report

International Nuclear Information System (INIS)

Cooper, D.W.; Evans, J.S.; Jacob, N.; Kase, K.R.; Maletskos, C.J.; Robertson, J.B.; Smith, D.G.

1983-03-01

This review of the radiological health effects models originally presented in the Reactor Safety Study (RSS) and currently used by the US Nuclear Regulatory Commission (NRC) was undertaken to assist the NRC in determining whether or not to revise the models and to aid in the revision, if undertaken. The models as presented in the RSS and as implemented in the CRAC (Calculations of Reactor Accident Consequences) Code are described and critiqued. The major elements analyzed are those concerning dosimetry, early effects, and late effects. The published comments on the models are summarized, as are the important findings since the publication of the RSS

eLearning-radiology.com. Sustainability for quality assurance; eLearning-radiology.com. Nachhaltigkeit im Sinne der Qualitaetssicherung

Energy Technology Data Exchange (ETDEWEB)

Ketelsen, D. [Tuebingen Univ. (Germany). Abt. fuer Diagnostische und Interventionelle Radiologie; Talanow, R. [Cleveland Clinic, Cleveland, OH (United States). Abt. fuer Nuklearmedizin; Uder, M. [Erlangen-Nuernberg Univ. (Germany). Inst. fuer Diagnostische Radiologie; Grunewald, M. [Erlangen-Nuernberg Univ. (Germany). Nuklearmedizinische Klinik

2009-04-15

Purpose: The aim of the study was to analyze the availability of published radiological e-learning tools and to establish a solution for quality assurance. Materials and Methods: Substantial pubmed research was performed to identify radiological e-learning tools. 181 e-learning programs were selected. As examples two databases expanding their programs with external links, Compare (n = 435 external links) and TNT-Radiology (n = 1078 external links), were evaluated. A concept for quality assurance was developed by an international taskforce. Results: At the time of assessment, 56.4 % (102/181) of the investigated e-learning tools were accessible at their original URL. A subgroup analysis of programs published 5 to 8 years ago showed significantly inferior availability to programs published 3 to 5 years ago (p < 0.01). The analysis of external links showed 49.2 % and 61.0 % accessible links for the programs Compare (published 2003) and TNT-Radiology (published 2006), respectively. As a consequence, the domain www.eLearning-radiology.com was developed by the taskforce and published online. This tool allows authors to present their programs and users to evaluate the e-learning tools depending on several criteria in order to remove inoperable links and to obtain information about the complexity and quality of the e-learning tools. (orig.)

Consequence analysis for nuclear reactors, Yongbyon

International Nuclear Information System (INIS)

Kang, Taewook; Jae, Moosung

2017-01-01

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

A model for the calculation of the off-site economic consequences of nuclear reactor accidents

International Nuclear Information System (INIS)

Gallego, E.; Alonso, A.

1988-01-01

The off-site economic cost of nuclear reactor accidents will depend on the countermeasures adopted to reduce its radiological impact. The assessment of the direct costs of emergency countermeasures (evacuation, early relocation and food disposal) as well as those of long-term protective actions (food disposal, decontamination or interdiction) is the objective of a model under development, with the sponsorship of the CEC Radiation Protection Programme, called MECA (Model for assessing the Economic Consequences of Accidents). The meteorological and socio-economical peculiarities of each site studied will be taken into account, by means of a flexible meteorological sampling scheme, which considers the geographical distribution of population and economic centers, and a data-base, compatible with the existing European grid, that contains the population distribution and the economic characteristics of the environs of the site to be studied with more detail near the reactor. The paper summarizes the particular models which will be included in MECA and shows the importance of site-specific adaptable modelling for economic risk evaluation

PRECLOSURE CONSEQUENCE ANALYSES FOR LICENSE APPLICATION

International Nuclear Information System (INIS)

S. Tsai

2005-01-01

Radiological consequence analyses are performed for potential releases from normal operations in surface and subsurface facilities and from Category 1 and Category 2 event sequences during the preclosure period. Surface releases from normal repository operations are primarily from radionuclides released from opening a transportation cask during dry transfer operations of spent nuclear fuel (SNF) in Dry Transfer Facility 1 (DTF 1), Dry Transfer Facility 2 (DTF 2), the Canister Handling facility (CHF), or the Fuel Handling Facility (FHF). Subsurface releases from normal repository operations are from resuspension of waste package surface contamination and neutron activation of ventilated air and silica dust from host rock in the emplacement drifts. The purpose of this calculation is to demonstrate that the preclosure performance objectives, specified in 10 CFR 63.111(a) and 10 CFR 63.111(b), have been met for the proposed design and operations in the geologic repository operations area. Preclosure performance objectives are discussed in Section 6.2.3 and are summarized in Tables 1 and 2

PRECLOSURE CONSEQUENCE ANALYSES FOR LICENSE APPLICATION

Energy Technology Data Exchange (ETDEWEB)

S. Tsai

2005-01-12

Radiological consequence analyses are performed for potential releases from normal operations in surface and subsurface facilities and from Category 1 and Category 2 event sequences during the preclosure period. Surface releases from normal repository operations are primarily from radionuclides released from opening a transportation cask during dry transfer operations of spent nuclear fuel (SNF) in Dry Transfer Facility 1 (DTF 1), Dry Transfer Facility 2 (DTF 2), the Canister Handling facility (CHF), or the Fuel Handling Facility (FHF). Subsurface releases from normal repository operations are from resuspension of waste package surface contamination and neutron activation of ventilated air and silica dust from host rock in the emplacement drifts. The purpose of this calculation is to demonstrate that the preclosure performance objectives, specified in 10 CFR 63.111(a) and 10 CFR 63.111(b), have been met for the proposed design and operations in the geologic repository operations area. Preclosure performance objectives are discussed in Section 6.2.3 and are summarized in Tables 1 and 2.

Significance and principles of the calculation of the effective dose equivalent for radiological protection of personnel and patients

International Nuclear Information System (INIS)

Drexler, G.; Williams, G.

1985-01-01

The application of the effective dose equivalent, Hsub(E), concept for radiological protection assessments of occupationally exposed persons is justifiable by the practicability thus achieved with regard to the limiting principles. Nevertheless, it would be proper logic to further use as the basic limiting quantity the real physical dose equivalent of homogeneous whole-body exposure, and for inhomogeneous whole-body irradiation the Hsub(E) value, calculated by means of the concept of the effective dose equivalent. For then the required concepts, models and calculations would not be connected with a basic radiation protection quantity. Application of the effective dose equivalent for radiation protection assessments for patients is misleading and is not practical with regard to assessing an individual or collective radiation risk of patients. The quantity of expected harm would be better suited to this purpose. There is no need to express the radiation risk by a dose quantity, which means careless handling of good information. (orig./WU) [de

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

Science.gov (United States)

Lääperi, A L

1996-01-01

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

Chernobyl ten years after-sum-up of the radiological and health effects as reported by IAEA and WHO

Energy Technology Data Exchange (ETDEWEB)

Koch, J [Israel Atomic Energy Commission, Yavne (Israel). Soreq Nuclear Research Center; Ilberg, D [Israel Atomic Energy Commission, Tel Aviv (Israel). Licensing Div.

1996-12-01

This paper will summarize the main findings presented by the scientific community at international conferences convened to sum-up the consequences of the Chernobyl accident at its tenth anniversary. It will only deal with the radiological and health consequences, as they were presented at the EC/lAEA/WHO International Conference `One Decade after Chernobyl` (Vienna, 8-12 April 1996) and the WHO International Conference on Health Consequences of the Chernobyl and Other Radiological Accident (authors).

Chernobyl ten years after-sum-up of the radiological and health effects as reported by IAEA and WHO

International Nuclear Information System (INIS)

Koch, J.; Ilberg, D.

1996-01-01

This paper will summarize the main findings presented by the scientific community at international conferences convened to sum-up the consequences of the Chernobyl accident at its tenth anniversary. It will only deal with the radiological and health consequences, as they were presented at the EC/lAEA/WHO International Conference 'One Decade after Chernobyl' (Vienna, 8-12 April 1996) and the WHO International Conference on Health Consequences of the Chernobyl and Other Radiological Accident (authors)

Lessons learned in radiology

International Nuclear Information System (INIS)

Goodenough, D.J.

2001-01-01

The paper reviews aspects of the history of radiology with the goal of identifying lessons learned, particularly in the area of radiological protection of the patient in diagnostic and interventional radiology, nuclear medicine and radiotherapy. It is pointed out that since the days of Roentgen there has been a need not only to control and quantify the amount of radiation reaching the patient but also to optimize the imaging process to offer the greatest diagnostic benefit within allowable levels of patient dose. To this end, in diagnostic radiology, one finds the development of better films, X rays tubes, grids, screens and processing techniques, while in fluoroscopy, one sees the increased luminance of calcium tungstate. In interventional radiology, one finds an improvement in catheterization techniques and contrast agents. In nuclear medicine, the development of tracer techniques into modern cameras and isotopes such as technetium can be followed. In radiotherapy, one sees the early superficial X rays and radium sources gradually replaced with radon seeds, supervoltage, 60 Co and today's linear accelerators. Along with the incredible advances in imaging and therapeutic technologies comes the growing realization of the potential danger of radiation and the need to protect the patient (as well as physicians, ancillary personnel and the general population) from unnecessary radiation. The important lesson learned is that we must walk a tightrope, balancing the benefits and risks of any technology utilizing radiation to produce the greatest benefits at the lowest acceptable risk. The alternative techniques using non-ionizing radiation will have to be considered as part of the general armamentarium for medical imaging whenever radiation consequences are unacceptable. (author)

Estimation of Radiological Terrorism Risk by Administrative Districts

Energy Technology Data Exchange (ETDEWEB)

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

2008-10-15

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

Estimation of Radiological Terrorism Risk by Administrative Districts

International Nuclear Information System (INIS)

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

2008-01-01

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

Metrology of radiation doses in diagnostic radiology

International Nuclear Information System (INIS)

Leclet, H.

2016-01-01

This article recalls how to calculate effective and equivalent doses in radiology from the measured value of the absorbed dose. The 97/43 EURATOM directive defines irradiation standards for diagnostic radiology (NRD) as the value of the radiation dose received by the patient's skin when the diagnostic exam is performed. NRD values are standard values that can be exceeded only with right medical or technical reasons, they are neither limit values nor optimized values. The purpose of NRD values is to avoid the over-irradiation of patients and to homogenize radiologists' practices. French laws impose how and when radiologists have to calculate the radiation dose received by the patient's skin. The calculated values have to be compared with NRD values and any difference has to be justified. A table gives NRD values for all diagnostic exams. (A.C.)

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

International Nuclear Information System (INIS)

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

1992-06-01

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

Guide for licensing evaluations using CRAC2: A computer program for calculating reactor accident consequences

International Nuclear Information System (INIS)

White, J.E.; Roussin, R.W.; Gilpin, H.

1988-12-01

A version of the CRAC2 computer code applicable for use in analyses of consequences and risks of reactor accidents in case work for environmental statements has been implemented for use on the Nuclear Regulatory Commission Data General MV/8000 computer system. Input preparation is facilitated through the use of an interactive computer program which operates on an IBM personal computer. The resulting CRAC2 input deck is transmitted to the MV/8000 by using an error-free file transfer mechanism. To facilitate the use of CRAC2 at NRC, relevant background material on input requirements and model descriptions has been extracted from four reports - ''Calculations of Reactor Accident Consequences,'' Version 2, NUREG/CR-2326 (SAND81-1994) and ''CRAC2 Model Descriptions,'' NUREG/CR-2552 (SAND82-0342), ''CRAC Calculations for Accident Sections of Environmental Statements, '' NUREG/CR-2901 (SAND82-1693), and ''Sensitivity and Uncertainty Studies of the CRAC2 Computer Code,'' NUREG/CR-4038 (ORNL-6114). When this background information is combined with instructions on the input processor, this report provides a self-contained guide for preparing CRAC2 input data with a specific orientation toward applications on the MV/8000. 8 refs., 11 figs., 10 tabs

PERSPECTIVES ON A DOE CONSEQUENCE INPUTS FOR ACCIDENT ANALYSIS APPLICATIONS

International Nuclear Information System (INIS)

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

2008-01-01

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

The sensitivity of calculated doses to critical assumptions for the offsite consequences of nuclear power reactor accidents

International Nuclear Information System (INIS)

Moeller, M.P.; Scherpelz, R.I.; Desrosiers, A.E.

1982-01-01

This work analyzes the sensitivity of calculated doses to critical assumptions for offsite consequences following a PWR-2 accident at a nuclear power reactor. The calculations include three radiation dose pathways: internal dose resulting from inhalation, external doses from exposure to the plume, and external doses from exposure to contaminated ground. The critical parameters are the time period of integration for internal dose commitment and the duration of residence on contaminated ground. The data indicate the calculated offsite whole body dose will vary by as much as 600% depending upon the parameters assumed. When offsite radiation doses determine the size of emergency planning zones, this uncertainty has significant effect upon the resources allocated to emergency preparedness

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

International Nuclear Information System (INIS)

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

1979-11-01

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

Quantitative evaluation of risks for individuals in diagnostic radiology

Energy Technology Data Exchange (ETDEWEB)

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

1980-05-01

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

Quantitative evaluation of risks for individuals in diagnostic radiology

International Nuclear Information System (INIS)

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

1980-01-01

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

Absorbed Doses to Embryo from Intravenous Urography at Selected Radiological Departments in Slovakia

International Nuclear Information System (INIS)

Karkus, R.; Nikodemova, D.; Horvathova, M.

2003-01-01

Actual legislation used in radiological protection requires quality assurance program for decreasing radiation load of patients from radiological examinations. The information about irradiation of pregnant women is very important, because the embryo is more radiosensitive as adult organism. On the basis of absence of unified calculations or measurements of absorbed doses to embryo from various radiological examinations in Slovakia we present in this study the values of absorbed doses to embryo from intravenous urography at selected radiological departments in Slovakia. Absorbed doses to embryo were obtained by measurement and calculation using the simulation of irradiation of pregnant woman by intravenous urography. The results of our study indicate, that absorbed doses to embryo were at various radiological departments considerably different, depending on type of X-ray machine and different settings of technical parameters of X-ray machine. In accordance with worldwide trend it is necessary to decrease radiation load of patients as low as possible level. Differences in radiation load between radiological departments indicate, that it is necessary to continue in solving of this problem and perform measurements and calculations of absorbed doses to embryo at different types of X-ray machines and at different examinations, where the embryo is in direct beam of X-ray. (author)

Interventional Radiology of Male Varicocele: Current Status

International Nuclear Information System (INIS)

Iaccarino, Vittorio; Venetucci, Pietro

2012-01-01

Varicocele is a fairly common condition in male individuals. Although a minor disease, it may cause infertility and testicular pain. Consequently, it has high health and social impact. Here we review the current status of interventional radiology of male varicocele. We describe the radiological anatomy of gonadal veins and the clinical aspects of male varicocele, particularly the physical examination, which includes a new clinical and ultrasound Doppler maneuver. The surgical and radiological treatment options are also described with the focus on retrograde and antegrade sclerotherapy, together with our long experience with these procedures. Last, we compare the outcomes, recurrence and persistence rates, complications, procedure time and cost-effectiveness of each method. It clearly emerges from this analysis that there is a need for randomized multicentre trials designed to compare the various surgical and percutaneous techniques, all of which are aimed at occlusion of the anterior pampiniform plexus.

Interventional Radiology of Male Varicocele: Current Status

Energy Technology Data Exchange (ETDEWEB)

Iaccarino, Vittorio, E-mail: vittorio.iaccarino@unina.it; Venetucci, Pietro [University of Naples ' Federico II' , Diagnostic Imaging Department-Cardiovascular and Interventional Radiology, School of Medicine (Italy)

2012-12-15

Varicocele is a fairly common condition in male individuals. Although a minor disease, it may cause infertility and testicular pain. Consequently, it has high health and social impact. Here we review the current status of interventional radiology of male varicocele. We describe the radiological anatomy of gonadal veins and the clinical aspects of male varicocele, particularly the physical examination, which includes a new clinical and ultrasound Doppler maneuver. The surgical and radiological treatment options are also described with the focus on retrograde and antegrade sclerotherapy, together with our long experience with these procedures. Last, we compare the outcomes, recurrence and persistence rates, complications, procedure time and cost-effectiveness of each method. It clearly emerges from this analysis that there is a need for randomized multicentre trials designed to compare the various surgical and percutaneous techniques, all of which are aimed at occlusion of the anterior pampiniform plexus.

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

International Nuclear Information System (INIS)

Franco, N.M.F.L.

1998-01-01

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

Radiological Dispersal Devices: Select Issues in Consequence Management

Science.gov (United States)

2004-03-10

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

Detriment calculations resulting from occupational radiation exposures in Egypt

International Nuclear Information System (INIS)

Abdel-Ghani, A.H.

2000-01-01

The application of the nominal probability coefficient to evaluate the detriment after the annual occupational exposures of workers from radiation sources and radioactive material have been calculated for workers in medical practices, industrial applications, atomic energy activities and those involved in exploration and mining of radioactive ores and phosphates. The aim of detriment calculations is to provide a foresight for the future occurrence of stochastic effects among the exposed workers. The calculated detriment can be classified into three classes. The first includes workers in diagnostic radiology and atomic energy activities who received the higher doses and consequently represent the higher detriment. The second class comprises workers in radiotherapy and nuclear medicine whose detriment is for times lesser than that of the first class. The third one concerns workers in industrial applications and in exploration and mining of radioactive ores and phosphates, their detriments ten times lesser than that of the second class. The occupational radiation doses are endorsed by the united nation scientific committee on efects of atomic radiation (UNSCEAR) for the period january 1995 to december 1998

A pilot study of radiation exposures arising from interventional radiology procedures

International Nuclear Information System (INIS)

Pellet, S.; Giczi, F.; Gaspardy, G.; Temesi, A.; Ballay, L.

2006-01-01

Full text of publication follows: In the past 25 years, considerable number of new therapeutic procedures have been worked out and adopted in radiology. These interventional procedures are mainly based on angiographic methods. During these procedures the exposure of patients and staff are usually greater than of conventional radiography and fluoroscopy as a consequence of longer fluoroscopy times and great number of cine-radiography. In the latest years radiation-induced skin injuries occurred in some patients. Injuries to physicians and staff performing interventional procedures have also been observed. In our days interventional procedures are widely used and more sophisticated procedures are worked out and adopted. Consequently, there is a need for the protection of the patient and the staff on a higher level. Radiation protection of intervention radiology deserves a distinguish attention. In Hungary interventional radiology were performed in 36 laboratories in 2003. According to statistical data the gross number of interventional radiological procedures were 19442. The most frequently performed procedures were the P.T.C.A., the coronary and ilio-femoral stent implantation and chemo-embolization. In 2004, the National Research Institute for Radiobiology and Radio-hygiene and the National Patient Dose Evaluation Program started a pilot study of radiation exposures arising from interventional radiology procedures. During the study the patient exposure were measured by D.A.P.-meters. The patient skin dose and the staff dose were performed by thermoluminescent chips. In their presentation the authors present the most important results of the study. (authors)

Radiological characterisation - Know your objective

International Nuclear Information System (INIS)

Lindow, Veronica; Moeller, Jennifer

2012-01-01

When developing a programme for mapping the radiological characteristics of a facility to be decommissioned it is important to take into account the objectives of the programme. Will the results be used to plan for radiological control and selection of appropriate decontamination and dismantling techniques? Will the radiological inventory be used for dimensioning of future waste repositories? These are two examples of the applications for such studies, which could require that a radiological characterisation programme be adapted to provide the data appropriate to the intended use. The level of detail and scope needed for a radiological characterisation will also vary depending on how the data will be used. An application to free-release a facility requires a comprehensive survey and well documented analysis in order to ensure that no radioactive contamination above prescribed levels is present. A bounding calculation to determine the maximum anticipated volumes and activity of radioactive waste requires a different approach. During the past few years, older decommissioning studies for the Swedish nuclear power plants have been updated (or are in the process of being updated). The decommissioning study's main purpose is to estimate the cost for decommissioning. The cost estimation is based on material and activity inventories, which in turn is based on previous and, in some cases, updated radiological characterisations of the facilities. The radiological inventory is an important part of the study as it affects the cost of decommissioning but also the uncertainties and accuracy of the cost estimation. The presentation will discuss the challenges in specifying a radiological characterisation programme with multiple objectives, together with insights on how data delivered can be applied to yield results suitable for the intended purpose, without introducing excessive conservatism. The intent of the presentation is to define issues that can be of use in various aspects

Emergency response during the radiological control of scraps in Cuba

International Nuclear Information System (INIS)

Ramos Viltre, Enma O.; Cardenas Herrera, Juan; Dominguez Ley, Orlando; Capote Ferrera, Eduardo; Fernandez Gomez, Isis M.; Caveda Ramos, Celia; Carrazana, Jorge; Barroso Perez, Idelisa

2008-01-01

In the last few years, in the international scene, incidents have been reported due to the presence of radioactive materials in the scrap. This reality has motivated the adoption of measures of radiological security, due to the implications that these incidents have for the public and the environment, as well as for the international trade. Among theses actions is the implementation of the radiological control of scrap, with the additional requirement that this control has to be implemented in the framework of a Quality Management Program.Taking into account the international experience, our institution designed and organized in 2002 a national service for the radiological monitoring of scrap, being the clients the main exporting and trading enterprises of this material in the country. During these years, several contaminated materials have been detected, causing incidents that activated the radiological emergency response system. In this sense, since some years ago, our country has been working in the implementation of a national and ministerial system for facing and mitigating the consequences of accidental radiological situations, conjugating efforts and wills from different national institutions with the leadership of the Center of Radiation Protection and Hygiene (CPHR) and the Center of Nuclear Security (CNSN) in correspondence with the social responsibility assigned to the them. These incidents propitiate to have not only a system of capacity and quick response oriented to limit the exposure of people, to control the sources, to mitigate the consequences of the accident and to reestablish the conditions of normality, but also a previous adequate planning that guarantees the speed and effectiveness of it. In these work the experiences reached by the specialists of the CPHR from Cuba during the occurrence of an incident in the execution of the service of radiological monitoring of scraps are exposed. (author)

Assessment of radiological risks at the ATLAS experiment

International Nuclear Information System (INIS)

Zajacova, Z.

2009-07-01

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

Long term radiological impact of a uranium mine restoration

International Nuclear Information System (INIS)

Mora, Veronica; Bordonaba Marisa; Sanchez Guillermo

2008-01-01

During the 1990s, many uranium mines were closed as consequence of low prices of this mineral. It was due to a decrease in the demand for uranium and an increase in the overall supply. The resulting was a further complicated implementation of sites restorations. This report deals with one of the relevant aspects of the radiological protection scope: 'the evaluation of the long term radiological impact in the population due to the uranium mine restoration activities' for the uranium mine sited in Saelices el Chico (Salamanca, Spain). These restoration activities have basically consisted of recovering the original site by filling the old open pits with the material stockpiled in the waste dumps. The main problems associated with this material include radon release and particles emission. The strategy used to solve this problem has been covered these structures with a layer with beds of clay material rock, waste material and a cover tree. The pathways considered for the radiological impact have been: 1) Inhalation; 2) Ingestion of contaminated water, milk, vegetables and meat; 3) External exposure from clouds immersion, grounds concentrations and direct gamma radiation. Three computer codes have been used with the object of evaluating the above-mentioned impact. Two of them are well-known NRC (Nuclear Regulatory Commission) codes: RESRAD 6.30 and MILDOS-AREA. We have also applied DOEFLURA, developed in ENUSA [1, 2, 3]. Four scenarios have been studied: Resident Farmer Scenario, Resident scenario, Livestock pasture scenario and Forest scenario, Estimation of radioactive doses for the member of the public in the different scenarios has been calculated with this programme. A period of 3500 years from now has been studied. (author)

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

International Nuclear Information System (INIS)

Jefferson, R.M.

1990-01-01

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

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

International Nuclear Information System (INIS)

Pickering, W.L.

2003-01-01

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

Calculation of radiation exposure in diagnostic radiology. Method and surveys

International Nuclear Information System (INIS)

Duvauferrier, R.; Ramee, A.; Ezzeldin, K.; Guibert, J.L.

1984-01-01

A computerized method for evaluating the radiation exposure of the main target organs during various diagnostic radiologic procedures is described. This technique was used for educational purposes: study of exposure variations according to the technical modalities of a given procedure, and study of exposure variations according to various technical protocols (IVU, EGD barium study, etc.). This method was also used for studying exposure of patients during hospitalization in the Rennes Regional Hospital Center (France) in 1982, according to departments (urology, neurology, etc.). This method and results of these three studies are discussed [fr

Radiological security for industrial radiography

International Nuclear Information System (INIS)

Montoya G, Manuel.

1985-04-01

This report comprises the basic notions of nucleonics, simple calculations for point sources, X-rays, calculations for coatings, standards for radiation protection and industrial radiography instruments. The preceding sums up with the biological effects of ionizing radiation. This is a guide for people who wish to pass examinations, to get the license for radiological safety, for operators on gamma-graphic sources, which work in the country. It is a requirement for work with this kind of radioactive sources

Report writing in skeletal radiology

International Nuclear Information System (INIS)

Rowe, L.J.; Yochum, T.R.

1987-01-01

The formulation of reports in clinical practice is a standard method of documentation of a patient's history, examination findings, therapeutic regime, and prognosis, as well as other important features. In the practice of producing and interpreting diagnostic radiographs, report writing also serves a number of important roles, which include providing an accurate means of recording findings in instances of 1) medicolegal circumstances; 2) a standard for comparison with previous or later examinations; 3) a permanent record if the radiographs are lost or not immediately available for perusal; 4) communication with other practitioners and health professionals; and 5) expediating the treatment regime by providing a resume of important indications and contraindictions for therapy. In the radiological literature there is a distinct lack of material on report writing and very little as to what would be considered a standard style. Consequently, radiological reporting has increasingly become a subjective, personalized procedure, with each individual modifying the report according to previous training, experience, and needs. It is the purpose of this chapter to provide basic guidelines on the mechanisms of formulating adequate standardized reports in radiological examinations of the skeletal system

[eLearning-radiology.com--sustainability for quality assurance].

Science.gov (United States)

Ketelsen, D; Talanow, R; Uder, M; Grunewald, M

2009-04-01

The aim of the study was to analyze the availability of published radiological e-learning tools and to establish a solution for quality assurance. Substantial pubmed research was performed to identify radiological e-learning tools. 181 e-learning programs were selected. As examples two databases expanding their programs with external links, Compare (n = 435 external links) and TNT-Radiology (n = 1078 external links), were evaluated. A concept for quality assurance was developed by an international taskforce. At the time of assessment, 56.4 % (102 / 181) of the investigated e-learning tools were accessible at their original URL. A subgroup analysis of programs published 5 to 8 years ago showed significantly inferior availability to programs published 3 to 5 years ago (p eLearning-radiology.com was developed by the taskforce and published online. This tool allows authors to present their programs and users to evaluate the e-learning tools depending on several criteria in order to remove inoperable links and to obtain information about the complexity and quality of the e-learning tools. More than 50 % of investigated radiological e-learning tools on the Internet were not accessible after a period of 5 to 8 years. As a consequence, an independent, international tool for quality assurance was designed and published online under www.eLearning-radiology.com .

Nuclear law and radiological accidents

International Nuclear Information System (INIS)

Frois, F.

1998-01-01

Nuclear activities in Brazil, and particularly the radiological accident of Goiania, are examined in the light of the environmental and nuclear laws of Brazil and the issue of responsibility. The absence of legislation covering radioactive wastes as well as the restrictions on Brazilian States to issue regulations covering nuclear activities are reviewed. The radiological accident and its consequences, including the protection and compensation of the victims, the responsibility of the shareholders of the Instituto Goiano de Radioterapia, operator of the radioactive source, the provisional storage and the final disposal at Abadia de Goias of the radioactive waste generated by the accident are reviewed. Finally, nuclear responsibility, the inapplicability of the Law 6453/77 which deals with nuclear damages, and the state liability regime are analysed in accordance with the principles of the Brazilian Federal Constitution. (author)

Radiological maps for Trabzon, Turkey

International Nuclear Information System (INIS)

Kurnaz, A.; Kucukomeroglu, B.; Damla, N.; Cevik, U.

2011-01-01

The activity concentrations and absorbed gamma dose rates due to primordial radionuclides and 137 Cs have been ascertained in 222 soil samples in 18 counties of the Trabzon province of Turkey using a HPGe detector. The mean activity concentrations of 238 U, 232 Th, 40 K and 137 Cs in soil samples were 41, 35, 437 and 21 Bq kg -1 , respectively. Based on the measured concentrations of these radionuclides, the mean absorbed gamma dose in air was calculated as 59 nGy h -1 and hence, the mean annual effective dose due to terrestrial gamma radiation was calculated as 72 μSv y -1 . In addition, outdoor in situ gamma dose rate (D) measurements were performed in the same 222 locations using a portable NaI detector and the annual effective dose was calculated to be 66 μSv y -1 from these results. The results presented in this study are compared with other parts of Turkey. Radiological maps of the Trabzon province were composed using the results obtained from the study. - Highlights: → →The study highlights activity concentrations of 238 U, 232 Th, 40 K and 137 Cs in soil. → The absorbed gamma dose in air and the mean annual effective dose were calculated. → The calculated results compared with outdoor in situ gamma dose measurements. → Radiological maps of the Trabzon province were created using ArcGIS applications. → The results will be valuable data for future estimations of radioactive pollution.

Implantation of a double reading process for radiological exams of the radiology service of the Clinical Hospital of Porto Alegre using the IMPAX client system

International Nuclear Information System (INIS)

Moraes, A.L.; Goulart, J.M.; Lucena, R.A.; Bacelar, A.; Pinto, A.L.A.

2017-01-01

A Quality Management System consists of several processes that qualify and quantify the performance of a service, minimizing the possibility of errors in the radiological diagnosis that may result in clinical consequences. One of these processes is the implantation of double reading, which consists in the evaluation of the report interpreted by a radiologist and the subsequent conference by another radiologist, through the analysis of archived PACS exams. The classification of the results of these analyzes was based on the recommendations of the American College of Radiology (ACR). Double reading is an extremely effective process for increasing the quality of the radiological report, in addition to contributing to the continuing education between the pairs

Method for consequence calculations for severe accidents

International Nuclear Information System (INIS)

Nielsen, F.

1988-07-01

This report was commissioned by the Swedish State Power Board. The report contains a calculation of radiation doses in the surroundings caused by a theoretical core meltdown accident at Forsmark reactor No 3. The accident sequence chosen for the calculating was a release caused by total power failure. The calculations were made by means of the PLUCON4 code. Meteorological data for two years from the Forsmark meteorological tower were analysed to find representative weather situations. As typical weather, Pasquill D was chosen with a wind speed of 5 m/s, and as extreme weather, Pasquill F with a wind speed of 2 m/s. 23 tabs., 37 ills., 20 refs. (author)

Science and values in radiological protection: impact on radiological protection decision making

International Nuclear Information System (INIS)

Salomaa, Sisko; Pinak, Miroslav

2008-01-01

Full text: This work summarises the main ideas and achievements of the Science and Values in Radiological Protection Workshop that was held on 15-17 January 2008 in Helsinki, Finland. In the view of developing of new radiological applications and emerging scientific phenomena it has been recognized a need to develop a shared understanding of emerging challenges for radiological protection among scientific and regulatory communities, public and other concerned stake holders. In response to this the Committee of Radiation Protection and Public Health of the OECD Nuclear Energy Agency and Radiation and Nuclear Safety Authority of Finland tried to initiate a process of longer-term reflection on scientific and societal issues that might challenge radiological protection in the coming years. Among general issues like radiological policy issues, improvement of understanding between research and policy communities, sharing views on emerging scientific issues, there were addressed several scientific issues, like non-targeted effects, individual sensitivity; and circulatory diseases. The main focus of these discussions was to elaborate potential 'what if' scenarios and propose feasible solutions at various levels. These discussions addressed effects that are not direct and evident consequence of the initial lesions produced at the cellular and DNA level like bystander responses, genomic instability, gene induction, adaptive responses and low dose. Particular interest was paid to an extrapolation of risk estimates to low doses and role of Linear Non-Threshold theory in setting regulatory principles. Individual radio-sensitivity and identification of genes that are suspected of having an influence on it were also discussed in one of the Breakout Sessions. Another Breakout Session addressed circulatory diseases. There is emerging evidence in the A-bomb survivors and in other exposed groups that ionising radiation also causes other diseases than cancer, such as circulatory

Radiological consequence of Chernobyl nuclear power accident in Japan

International Nuclear Information System (INIS)

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

1988-03-01

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

Design of software for calculation of shielding based on various standards radiodiagnostic calculation

International Nuclear Information System (INIS)

Falero, B.; Bueno, P.; Chaves, M. A.; Ordiales, J. M.; Villafana, O.; Gonzalez, M. J.

2013-01-01

The aim of this study was to develop a software application that performs calculation shields in radiology room depending on the type of equipment. The calculation will be done by selecting the user, the method proposed in the Guide 5.11, the Report 144 and 147 and also for the methodology given by the Portuguese Health Ministry. (Author)

Terrorism: the threat of a radiological device

International Nuclear Information System (INIS)

Kingshott, B.F.

2005-01-01

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

Method for consequence calculations for severe accidents

International Nuclear Information System (INIS)

Nielsen, F.; Thykier-Nielsn, S.

1987-03-01

This report was commissioned by the Swedish State Power Board. The report contains a calculation of radiation doses in the surroundings caused by a theoretical core meltdown accident at Forsmark reactor No 3. The assumption used for the calculations were a 0.06% release of iodine and cesium corresponding to a 0.1% release through the FILTRA plant at Barsebaeck. The calculations were made by means of the PLUCON4 code. Meteorological data for two years from the Forsmark meteorological tower were analysed to find representative weather situations. As typical weather pasquill D was chosen with wind speed 5 m/s, and as extreme weather, Pasquill F with wind speed 2 m/s. 23 tabs., 36 ills., 21 refs. (author)

RADTRAN 6 Technical Manual

Energy Technology Data Exchange (ETDEWEB)

Weiner, Ruth F. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Neuhauser, Karen Sieglinde [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Heames, Terence John [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); O' Donnell, Brandon M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Dennis, Matthew L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2014-01-01

This Technical Manual contains descriptions of the calculation models and mathematical and numerical methods used in the RADTRAN 6 computer code for transportation risk and consequence assessment. The RADTRAN 6 code combines user-supplied input data with values from an internal library of physical and radiological data to calculate the expected radiological consequences and risks associated with the transportation of radioactive material. Radiological consequences and risks are estimated with numerical models of exposure pathways, receptor populations, package behavior in accidents, and accident severity and probability.

RADTRAN 6 technical manual.

Energy Technology Data Exchange (ETDEWEB)

Weiner, Ruth F.; Neuhauser, Karen Sieglinde; Heames, Terence John; O' Donnell, Brandon M.; Dennis, Matthew L.

2014-01-01

This Technical Manual contains descriptions of the calculation models and mathematical and numerical methods used in the RADTRAN 6 computer code for transportation risk and consequence assessment. The RADTRAN 6 code combines user-supplied input data with values from an internal library of physical and radiological data to calculate the expected radiological consequences and risks associated with the transportation of radioactive material. Radiological consequences and risks are estimated with numerical models of exposure pathways, receptor populations, package behavior in accidents, and accident severity and probability.

Criteria and actions facing a radiological environmental contamination

International Nuclear Information System (INIS)

Gutierrez, Jose; Montero, Milagros

2008-01-01

An approach to improve the management of the radiological risk due to an environmental contamination is presented. The experience gained in emergency response has clearly demonstrated the importance to have an efficient emergency system including planning, procedures and operational internally consistent criteria. The lack of these components in the emergency system could lead to important radiological and non radiological consequences. The setting of internationally agreed criteria and guides is very important in the anticipated emergency response plan. The paper firstly reviews the approaches proposed by international recommendations and norms. From this review, a substantial coincidence on the basic principles is stated, in spite of small differences in its formulation. Also, a need for harmonization is endorsed. So, generic levels, in terms of imparted dose or avoided dose due to intervention, and, in some cases, derived levels, in terms of activity concentration, are proposed. Numerical values for emergency actions are also identified. The second part deals with the adaptation of the existing prediction and decision systems to the above radiological criteria. Relations among deposition, activity concentrations and annual doses for different scenarios, exposure pathways and age groups are established. Also, the sensibility of the radiological impact against different characteristics of the intervention scenarios is stated. This makes easy to assess the radiological significance of different contamination situations by comparison to the existing action generic levels. Furthermore, the radiological impact can be numerically incorporated in a decision system which includes non radiological aspects of the applicable intervention options. Agricultural, urban and mixed scenarios are presented and solved for a 137 Cs contamination. The results can be further used to develop a methodology guide for setting action generic levels in post-accidental interventions and

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

International Nuclear Information System (INIS)

Anon.

1974-01-01

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

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

International Nuclear Information System (INIS)

Anon.

1974-01-01

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

Radiology today

International Nuclear Information System (INIS)

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

1981-01-01

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

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)

eLearning-radiology.com. Sustainability for quality assurance

International Nuclear Information System (INIS)

Ketelsen, D.; Talanow, R.; Uder, M.; Grunewald, M.

2009-01-01

Purpose: The aim of the study was to analyze the availability of published radiological e-learning tools and to establish a solution for quality assurance. Materials and Methods: Substantial pubmed research was performed to identify radiological e-learning tools. 181 e-learning programs were selected. As examples two databases expanding their programs with external links, Compare (n = 435 external links) and TNT-Radiology (n = 1078 external links), were evaluated. A concept for quality assurance was developed by an international taskforce. Results: At the time of assessment, 56.4 % (102/181) of the investigated e-learning tools were accessible at their original URL. A subgroup analysis of programs published 5 to 8 years ago showed significantly inferior availability to programs published 3 to 5 years ago (p < 0.01). The analysis of external links showed 49.2 % and 61.0 % accessible links for the programs Compare (published 2003) and TNT-Radiology (published 2006), respectively. As a consequence, the domain www.eLearning-radiology.com was developed by the taskforce and published online. This tool allows authors to present their programs and users to evaluate the e-learning tools depending on several criteria in order to remove inoperable links and to obtain information about the complexity and quality of the e-learning tools. (orig.)

Laboratory of environmental radiological surveillance; Laboratorio de vigilancia radiologica ambiental

Energy Technology Data Exchange (ETDEWEB)

Mendez G, A; Marcial M, F; Giber F, J; Montiel R, E; Leon del V, E; Rivas C, I; Leon G, M V; Lagunas G, E; Aragon S, R; Juarez N, A; Alfaro L, M M

1991-12-15

The department of radiological protection of the ININ requests the collaboration of the Engineering Unit for the elaboration of the work project of the laboratory of environmental radiological surveillance. The emission of radioactive substances to the atmosphere like consequence of the normal operation of the Nuclear Center, constitutes an exhibition source from the man to the radiations that it should be appropriately watched over and controlled to be able to determine the population's potential exhibition that it lives in the area of influence of the installation. (Author)

Radiological Protection Science and Application

International Nuclear Information System (INIS)

Janssens, Augustin; ); Mossman, Ken; Morgan, Bill

2016-01-01

importance of stakeholder involvement and individual and societal values in radiological protection decision making, Chapter 2 of this report addresses the societal aspects of radiological protection decision making. Chapter 3 addresses the application-related aspects of radiological protection. These include existing exposure situations, planned exposure situations, emergency exposure situations and environmental radiological protection. Chapter 4 of the report addresses international standards and Chapter 5 provides CRPPH views on overall ways forward. Annex A provides a more detailed overview of the International Commission on Radiological Protection (ICRP) system of radiological protection, its interpretation in the International Basic Safety Standards (IBSS) and in the Euratom Basic Safety Standards (Euratom BSS). It demonstrates how the ICRP system may be influenced by both an evolving science and society, and in particular by the increasing focus on addressing protection in the context of prevailing circumstances. Each chapter of this report was prepared by experts on the topic, and an attempt has been made to follow a common framework. Having a common framework for chapters addressing science and those addressing implementation proved to be particularly difficult. As a consequence, the report's structure is constructed in such a way so as to address the state of the art in each area, while attempting to present aspects under broadly common headlines. (authors)

Radiological protection in underground uranium mines

International Nuclear Information System (INIS)

Napolitano, Celia Marina

1978-01-01

The radiosanitary hazards that workers of an uranium ore can suffer were studied. The more used control methods for the the evaluation of doses received by the workers was studied too. It was developed a technique using the scintillation chamber method for the detection of radon. Emanation and diffusion methods were used for extraction of radon from water. A program of radiological protection based on ICRP recommendation was analysed for uranium mines. This program includes: ventilation needs calculation methods, a study of radiological protection optimization based on 'cost-benefit' analysis, a monitoring plan and a study about radioactive waste management. (author)

Report on the research through the U.S.DOE. 'The international search and consequence management workshop (ISCM-WS)'

International Nuclear Information System (INIS)

Kawakami, Takeshi; Tasaki, Takashi

2011-12-01

The International Search and Consequence Management Workshop (ISCM-WS) that was organized by the U.S. Department of Energy (DOE) took place from May 17th to May 20th, 2010. The aim of this Workshop was to build and enhance the global capacity to prevent and respond to nuclear and radiological emergencies, and it directly supports the aims of global initiative to combat nuclear terrorism. The U.S.DOE brought together 92 officials from 26 countries and 3 officials from IAEA in this workshop. DOE introduced two matters in the USA, first was response against nuclear and radiological terrorisms and second was technology, systems, activity for consequence management. This Review Report summarized the observation of the ISCM-WS including activity of DOE/NNSA's Search Response Team and activity of consequence management. Important knowledge from the ISCM-WS is as follows: Development and Equipment of remote radiation measurement system for searching Improvised Nuclear devises, Radiological Dispersal Device, etc. Using GPS data for mapping and checking of radiation measurement, Using GIS system for supporting planning and mapping of radiation measurement. Follow up system for checking first responder's radiation measurement data by radiological specialist in the radiological institute at distance place. Deployment system and logistics system for radiation monitoring team and radiation management team including national agency's team who are deployed on the spot. Aerial Measuring System and mobile laboratory for environmental samples analysis. Information sharing system for consequence management. (author)

Radiological characterization for small type light water reactor

International Nuclear Information System (INIS)

Tanaka, Ken-ichi; Ichige, Hideaki; Tanabe, Hidenori

2011-01-01

In order to plan a decommissioning, amount investigation of waste materials and residual radioactivity inventory evaluation must be performed at the first stage of preparatory tasks. These tasks are called radiological characterization. Reliable information from radiological characterization is crucial for specification of decommissioning plan. With the information, we can perform radiological safety analysis and optimize decommissioning scenario. Japan Atomic Power Company (JAPC) has already started preparatory tasks for Tsuruga Nuclear Power Plant Unit 1 (TS-1) that is the first commercial Small Type Light Water Reactor in Japan. To obtain reliable information about residual radioactivity inventory, we improved radioactivity inventory evaluation procedure. The procedure consists of neutron flux distribution calculation and radioactivity distribution calculation. We need a better understanding about characteristics of neutron transport phenomena in order to obtain reliable neutron flux distribution. Neutron flux was measured in Primary Containment Vessel (PCV) at 30 locations using activation foils. We chose locations where characteristic phenomena can be observed. Three dimensional (3D) neutron flux calculation was also performed to simulate continuous changes of neutron flux distribution. By assessing both the measured values and 3D calculation results, we could perform the calculation that simulates the phenomena well. We got knowledge about how to perform an appropriate neutron flux distribution calculation and also became able to calculate a reliable neutron flux distribution. Using the neutron flux distribution, we can estimate a reliable radioactivity distribution. We applied network-parallel-computing method to the estimation. And further we developed 'flux level approximation method' which use linear or parabola fitting method to estimation. Using these new methods, radioactivity by neutron irradiation, which is radioisotope formation, was calculated at

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

Ensuring the safety of surgical teams when managing casualties of a radiological dirty bomb.

Science.gov (United States)

Williams, Geraint; O'Malley, Michael; Nocera, Antony

2010-09-01

The capacity for surgical teams to ensure their own safety when dealing with the consequences caused by the detonation of a radiological dirty bomb is primarily determined by prior knowledge, familiarity and training for this type of event. This review article defines the associated radiological terminology with an emphasis on the personal safety of surgical team members in respect to the principles of radiological protection. The article also describes a technique for use of hand held radiation monitors and will discuss the identification and management of radiologically contaminated patients who may pose a significant danger to the surgical team. 2010 Elsevier Ltd. All rights reserved.

Internal Controlling of a Radiology Department.

Science.gov (United States)

Frewer, W; Busch, H P

2015-11-01

Caused by legal reform initiatives there is a continuous need to increase effectiveness and efficiency in hospitals and surgeries, and thus to improve processes.Consequently the successful management of radiological departments and surgeries requires suitable structures and optimization processes to make optimization in the fields of medical quality, service quality and efficiency possible.In future in the DRG System it is necessary that the organisation of processes must focus on the whole clinical treatment of the patients (Clinical Pathways). Therefore the functions of controlling must be more established and adjusted. On the basis of select Controlling instruments like budgeting, performance indicators, process optimization, staff controlling and benchmarking the target-based and efficient control of radiological surgeries and departments is shown. © Georg Thieme Verlag KG Stuttgart · New York.

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

International Nuclear Information System (INIS)

Maul, P.R.

1984-03-01

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

Radiological Dose Calculations And Supplemental Dose Assessment Data For Neshap Compliance For SNL Nevada Facilities 1996.

Energy Technology Data Exchange (ETDEWEB)

None, None

2017-05-01

Operations of Sandia National Laboratories, Nevada (SNL/NV) at the Tonopah Test Range (TTR) resulted in no planned point radiological releases during 1996. Other releases from SNL/NV included diffuse transuranic sources consisting of the three Clean Slate sites. Air emissions from these sources result from wind resuspension of near-surface transuranic contaminated soil particulates. The total area of contamination has been estimated to exceed 20 million square meters. Soil contamination was documented in an aerial survey program in 1977 (EG&G 1979). Surface contamination levels were generally found to be below 400 pCi/g of combined plutonium-238, plutonium-239, plutonium-240, and americium-241 (i.e., transuranic) activity. Hot spot areas contain up to 43,000 pCi/g of transuranic activity. Recent measurements confirm the presence of significant levels of transuranic activity in the surface soil. An annual diffuse source term of 0.39 Ci of transuranic material was calculated for the cumulative release from all three Clean Slate sites. A maximally exposed individual dose of 1.1 mrem/yr at the TTR airport area was estimated based on the 1996 diffuse source release amounts and site-specific meteorological data. A population dose of 0.86 person-rem/yr was calculated for the local residents. Both dose values were attributable to inhalation of transuranic contaminated dust.

Radiology applications of financial accounting.

Science.gov (United States)

Leibenhaut, Mark H

2005-03-01

A basic knowledge of financial accounting can help radiologists analyze business opportunities and examine the potential impacts of new technology or predict the adverse consequences of new competitors entering their service area. The income statement, balance sheet, and cash flow statement are the three basic financial statements that document the current financial position of the radiology practice and allow managers to monitor the ongoing financial operations of the enterprise. Pro forma, or hypothetical, financial statements can be generated to predict the financial impact of specific business decisions or investments on the profitability of the practice. Sensitivity analysis, or what-if scenarios, can be performed to determine the potential impact of changing key revenue, investment, operating cost or financial assumptions. By viewing radiology as both a profession and a business, radiologists can optimize their use of scarce economic resources and maximize the return on their financial investments.

Pediatric radiology for medical-technical radiology assistants/radiologists

International Nuclear Information System (INIS)

Oppelt, Birgit

2010-01-01

The book on pediatric radiology includes the following chapter: differences between adults and children; psycho-social aspects concerning the patient child in radiology; relevant radiation doses in radiology; help for self-help: simple phantoms for image quality estimation in pediatric radiology; general information; immobilization of the patient; pediatric features for radiological settings; traumatology; contrast agents; biomedical radiography; computerized tomography; NMR imaging; diagnostic ultrasonography; handling of stress practical recommendations; medical displays.

The radiological management of the thrombosed arteriovenous dialysis fistula

Energy Technology Data Exchange (ETDEWEB)

Bent, C.L., E-mail: clare_bent@yahoo.co.u [Royal Bournemouth and Christchurch Hospitals, Bournemouth (United Kingdom); Sahni, V.A. [Division of Abdominal Imaging and Intervention, Department of Radiology, Brigham and Women' s Hospital, Harvard Medical School, Boston (United States); Matson, M.B. [Barts and The London NHS Trust, London (United Kingdom)

2011-01-15

Patent vascular access is a prerequisite for adequate haemodialysis, and is a major determinant of quality of life and long-term survival of patients with end-stage renal disease. Autogenous haemodialysis fistulas (AVFs) have demonstrated superior clinical outcome when compared to synthetic grafts, but both types of access remain susceptible to venous stenoses, and consequent thrombotic occlusion. Recent publications have reported primary patency rates of up to 100% following percutaneous de-clotting of AVFs incorporating techniques such as pharmacological thrombolysis, mechanical thrombectomy, and thrombo-aspiration. Endovascular management also provides information regarding the underlying cause of access thrombosis, with option to treat. Consequently, there has been a paradigm shift in the management of fistula thrombosis, with interventional radiology assuming a lead role in initial salvage procedures. This article will attempt to provide the reader with an insight into the multiple radiological techniques that can be employed to salvage a thrombosed AVF based on current published literature.

The radiological management of the thrombosed arteriovenous dialysis fistula

International Nuclear Information System (INIS)

Bent, C.L.; Sahni, V.A.; Matson, M.B.

2011-01-01

Patent vascular access is a prerequisite for adequate haemodialysis, and is a major determinant of quality of life and long-term survival of patients with end-stage renal disease. Autogenous haemodialysis fistulas (AVFs) have demonstrated superior clinical outcome when compared to synthetic grafts, but both types of access remain susceptible to venous stenoses, and consequent thrombotic occlusion. Recent publications have reported primary patency rates of up to 100% following percutaneous de-clotting of AVFs incorporating techniques such as pharmacological thrombolysis, mechanical thrombectomy, and thrombo-aspiration. Endovascular management also provides information regarding the underlying cause of access thrombosis, with option to treat. Consequently, there has been a paradigm shift in the management of fistula thrombosis, with interventional radiology assuming a lead role in initial salvage procedures. This article will attempt to provide the reader with an insight into the multiple radiological techniques that can be employed to salvage a thrombosed AVF based on current published literature.

Laboratory of environmental radiological surveillance; Laboratorio de vigilancia radiologica ambiental

Energy Technology Data Exchange (ETDEWEB)

Mendez G, A.; Marcial M, F.; Giber F, J.; Montiel R, E.; Leon del V, E.; Rivas C, I.; Leon G, M.V.; Lagunas G, E.; Aragon S, R.; Juarez N, A.; Alfaro L, M.M

1991-12-15

The department of radiological protection of the ININ requests the collaboration of the Engineering Unit for the elaboration of the work project of the laboratory of environmental radiological surveillance. The emission of radioactive substances to the atmosphere like consequence of the normal operation of the Nuclear Center, constitutes an exhibition source from the man to the radiations that it should be appropriately watched over and controlled to be able to determine the population's potential exhibition that it lives in the area of influence of the installation. (Author)

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

Energy Technology Data Exchange (ETDEWEB)

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

1992-06-01

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

An advanced microcosting system for forecasting and managing radiology expenses

International Nuclear Information System (INIS)

Arenson, R.; Viale, R.; VanDerVoorde, F.

1985-01-01

The new prospective payment system encourages hospital cost containment and necessitates understanding actual cost for radiology procedures. The automated microcosting system described in this paper, utilizing data from the Radiology Information Management System, hospital expense reports, and payroll management reports, calculates an accurate unit cost for each procedure type. This data is very useful for cost control, enhancement of department efficiency, and planning

Intelligent image retrieval based on radiology reports

Energy Technology Data Exchange (ETDEWEB)

Gerstmair, Axel; Langer, Mathias; Kotter, Elmar [University Medical Center Freiburg, Department of Diagnostic Radiology, Freiburg (Germany); Daumke, Philipp; Simon, Kai [Averbis GmbH, Freiburg (Germany)

2012-12-15

To create an advanced image retrieval and data-mining system based on in-house radiology reports. Radiology reports are semantically analysed using natural language processing (NLP) techniques and stored in a state-of-the-art search engine. Images referenced by sequence and image number in the reports are retrieved from the picture archiving and communication system (PACS) and stored for later viewing. A web-based front end is used as an interface to query for images and show the results with the retrieved images and report text. Using a comprehensive radiological lexicon for the underlying terminology, the search algorithm also finds results for synonyms, abbreviations and related topics. The test set was 108 manually annotated reports analysed by different system configurations. Best results were achieved using full syntactic and semantic analysis with a precision of 0.929 and recall of 0.952. Operating successfully since October 2010, 258,824 reports have been indexed and a total of 405,146 preview images are stored in the database. Data-mining and NLP techniques provide quick access to a vast repository of images and radiology reports with both high precision and recall values. Consequently, the system has become a valuable tool in daily clinical routine, education and research. (orig.)

Intelligent image retrieval based on radiology reports

International Nuclear Information System (INIS)

Gerstmair, Axel; Langer, Mathias; Kotter, Elmar; Daumke, Philipp; Simon, Kai

2012-01-01

To create an advanced image retrieval and data-mining system based on in-house radiology reports. Radiology reports are semantically analysed using natural language processing (NLP) techniques and stored in a state-of-the-art search engine. Images referenced by sequence and image number in the reports are retrieved from the picture archiving and communication system (PACS) and stored for later viewing. A web-based front end is used as an interface to query for images and show the results with the retrieved images and report text. Using a comprehensive radiological lexicon for the underlying terminology, the search algorithm also finds results for synonyms, abbreviations and related topics. The test set was 108 manually annotated reports analysed by different system configurations. Best results were achieved using full syntactic and semantic analysis with a precision of 0.929 and recall of 0.952. Operating successfully since October 2010, 258,824 reports have been indexed and a total of 405,146 preview images are stored in the database. Data-mining and NLP techniques provide quick access to a vast repository of images and radiology reports with both high precision and recall values. Consequently, the system has become a valuable tool in daily clinical routine, education and research. (orig.)

Method for consequence calculations for servere accidents

International Nuclear Information System (INIS)

Nielsen, F.

1987-01-01

With the exception of the part about collective doses, this report was commissioned by the Swedish State Power Board. The part about collective doses was commissioned by the Swedish National Institute of Radiation Protection. The report contains a calculation of radiation doses in the sursurroundings caused by a theoretical core meltdown accident at one of the Barsebaeck reactors with filtered venting through the FILTRA plant. The calculations were made by means of the PLUCON4 code. The assumption used for the calculations were givon by the Swedish National Institute of Radiation Protection as follows: Pasquill D with wind speed 3 m/s and a mixing layer at 300 m height. Elevation of the release: 100 m with no energy release. The release starts 12 hours after shut-down and its duration is one hour. The release contains 100% of the noble gasses and 0,1% of all other isotopes in a 1800 MW t -reactor. (author)

Environmental consequences of alternatives to L Reactor restart

International Nuclear Information System (INIS)

1983-01-01

Alternatives to renewed L-Reactor operation for increased production of nuclear materials are: restart of R Reactor, construction and operation of a New Production Reactor (NPR), increased throughput of SRP reactors C, K, and P and N Reactor at Hanford, restart of K Reactors at Hanford, and no action - standby ready state for L Reactor. This report compares the environmental consequences from the proposed L-Reactor restart and these alternatives. The environmental consequences considered are radiological releases, radiocesium remobilization, nonradiological releases, ecological impacts and transportation

Modeling of radionuclide transport through rock formations and the resulting radiation exposure of reference persons. Calculations using Asse II parameters

International Nuclear Information System (INIS)

Kueppers, Christian; Ustohalova, Veronika; Steinhoff, Mathias

2012-01-01

The long-term release of radioactivity into the ground water path cannot be excluded for the radioactive waste repository Asse II. The possible radiological consequences were analyzed using a radio-ecological scenario developed by GRS. A second scenario was developed considering the solubility of radionuclides in salt saturated solutions and retarding/retention effects during the radionuclide transport through the cap rock layers. The modeling of possible radiation exposure was based on the lifestyle habits of reference persons. In Germany the calculation procedure for the prediction of radionuclide release from final repositories is not defined by national standards, the used procedures are based on analogue methods from other radiation protection calculations.

Radiological accident 'The Citadel' medical aspects

International Nuclear Information System (INIS)

Cardenas Herrera, Juan; Fernandez, Isis M.; Lopez, Gladys; Garcia, Omar; Lamadrid, Ana I.; Ramos, Enma O.; Villa, Rosario; Giron, Carmen M.; Escobar, Myrian; Zerpa, Miguel; Romero, Argenis H.; Medina, Julio; Laurenti, Zenia; Oliva, Maria T.; Sierra, Nitza; Lorenzo, Alexis

2008-01-01

The work exposes the medical actions carried out in the mitigation of the consequences of the accident and its main results. In a facility of storage of radioactive waste in Caracas, Venezuela, it was happened a radiological accident. This event caused radioactive contamination of the environment, as well as the irradiation and radioactive contamination of at least 10 people involved in the fact, in its majority children. Cuban institutions participated in response to the accident. Among the decisions adopted by the team of combined work Cuban-Venezuelan, we find the one of transferring affected people to Cuba, for their dosimetric and medical evaluation. Being designed a work strategy to develop the investigations to people affected by the radiological accident, in correspondence with the circumstances, magnitude and consequences of the accident. The obtained main results are: 100% presented affectations in its health, not associate directly to the accident, although the accident influenced in its psychological state. In 3 of studied people they were detected radioactive contamination with Cesium -137 with dose among 2.01 X 10-4 Sv up to 2.78 X 10-4 Sv. This accident demonstrated the necessity to have technical capacities to face these events and the importance of the international solidarity. (author)

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

Evaluation of atmospheric dispersion/consequence models supporting safety analysis

International Nuclear Information System (INIS)

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

1996-01-01

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

On the radiology of thorium-uranium electro breeding

International Nuclear Information System (INIS)

Gai, E.V.; Rabotnov, N.S.; Shubin, Y.N.

1995-01-01

Radiological problems arising in thorium-uranium electro-breeding with thorium accelerator target are discussed. Following radiological problems are discussed and evaluated in simplified model calculations: U-232 formation, accumulation of light Th isotopes in (n, xn) reactions on thorium target: accumulation of the same nuclides in final repository after alpha-decay of uranium isotopes. The qualitative comparison of U-Pu and U-Th fuel cycles is performed. The problems seem to be serious enough to justify detailed quantitative investigation. (authors)

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)

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

International Nuclear Information System (INIS)

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

1987-01-01

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

A guide to TIRION 4 - a computer code for calculating the consequences of releasing radioactive material to the atmosphere

International Nuclear Information System (INIS)

Fryer, L.S.

1978-12-01

TIRION 4 is the most recent program in a series designed to calculate the consequences of releasing radioactive material to the atmosphere. A brief description of the models used in the program and full details of the various control cards necessary to run TIRION 4 are given. (author)

Radiological Worker Training: Radiological Worker 2 study guides

International Nuclear Information System (INIS)

1992-10-01

Upon completion of this training course, the participant will have the knowledge to work safely in areas controlled for radiological purposes using proper radiological practices. Radiological Worker H Training, for the worker whose job assignment involves entry into Radiological Buffer Areas and all types of Radiation Contamination and Airborne Radioactivity Areas. This course is designed to prepare the worker to work safely in and around radiological areas and present methods to use to ensure individual radiation exposure is maintained As Low As Reasonably Achievable

Radiological Effluent Technical Specifications (RETS) implementation, Kewaunee Nuclear Power Plant

International Nuclear Information System (INIS)

Serrano, W.; Akers, D.W.

1985-06-01

A review of the Radiological Effluent Technical Specifications (RETS) for the Kewaunee Nuclear Power Plant was performed. The principal review guidelines used were NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,'' and Draft 7'' of NUREG-0472, Revision 3, ''Radiological Effluent Technical Specifications for Pressurized Water Reactors.'' Draft submittals were discussed with the Licensee by the NRC staff until all items requiring changes to the Technical Specifications were resolved. The Licensee then submitted final proposed RETS to the NRC which were evaluated and found to be in compliance with the NRC review guidelines. The proposed Offsite Dose Calculation Manual and the Radiological Environmental Monitoring Manual were reviewed and generally found to be in compliance with the NRC review guidelines

Radiological Source Terms for Tank Farms Safety Analysis

Energy Technology Data Exchange (ETDEWEB)

COWLEY, W.L.

2000-06-27

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

Radiological clerkships as a critical curriculum component in radiology education

International Nuclear Information System (INIS)

Kourdioukova, Elena V.; Verstraete, Koenraad L.; Valcke, Martin

2011-01-01

Objective: The aim of this research was to explore the perceived value of clinical clerkships in the radiology curriculum as well as the impact of radiology clerkship on students' beliefs about the profession of radiology as a whole and as a career. Methods: This study is a sequel to a previous survey in which student perceptions about radiology curriculum components were investigated. The present study focuses on a further analysis of a subsection in this study, based on 14 statements about radiology clerkship and two statements about radiology as a career. Results: Perceived usefulness of the aspects of radiology clerkship as 'radiology examination', 'skills development' and 'diagnosis focus' were awarded the highest scores. The predict value of the subscale 'radiology examination' on the level of performance was very high (adjusted R 2 = 0.19, p < .001). Conclusion: Students expressed highly favorable evaluation of clerkship as a learning environment to learn to order and to interpret imaging studies as well as an unique possibility to attend various radiological examinations and to access to specific radiology software systems, as well as to get a better view on radiology and to improve image interpretation skills. This positive attitude towards clerkship is closely tied to students' beliefs about the profession of radiology as a whole. These aspects of dedicated radiology clerkship are crucial for effective and high-quality education as well as for the choice of radiology as a career.

Diagnostic radiology 1987

International Nuclear Information System (INIS)

Margulis, A.R.; Gooding, C.A.

1987-01-01

This is the latest version of the continuing education course on diagnostic radiology given yearly by the Department of Radiology at the University of California, San Francisco. The lectures are grouped into sections on gastrointestinal radiology, mammography, uroradiology, magnetic resonance, hepatobiliary radiology, pediatric radiology, ultrasound, interventional radiology, chest radiology, nuclear medicine, cardiovascular radiology, and skeletal radiology. Each section contains four to eight topics. Each of these consists of text that represents highlights in narrative form, selected illustrations, and a short bibliography. The presentation gives a general idea of what points were made in the lecture

Software for the estimation of organ equivalent and effective doses from diagnostic radiology procedures

International Nuclear Information System (INIS)

Osei, Ernest K; Barnett, Rob

2009-01-01

Diagnostic radiological imaging such as conventional radiography, fluoroscopy and computed tomography (CT) examinations will continue to provide tremendous benefits in modern healthcare. The benefit derived by the patient should far outweigh the risk associated with a properly conducted imaging examination. Nonetheless, it is very important to be able to quantify the risk associated with any radiological examination of patients, and effective dose has been considered a useful indicator of patient exposure. Quantification of the risks associated with radiological imaging is very important as such information will be helpful to physicians and their patients for comparing risks from various imaging examinations and for making informed decisions whenever there is a need for any radiological imaging. The determination of equivalent and effective doses in diagnostic radiology is of interest as a basis for estimates of risk from medical exposures. In this paper we describe a simple computer program OrgDose, which calculates the doses to 27 organs in the body and then calculates the organ equivalent and effective doses and the risk from various procedures in the radiology department including conventional radiography, fluoroscopy and computed tomography examinations. The program will be a useful tool for the medical and paramedical personnel who are involved with assessing organ and effective doses and risks from diagnostic radiology procedures.

Radioactive cloud dose calculations

International Nuclear Information System (INIS)

Healy, J.W.

1984-01-01

Radiological dosage principles, as well as methods for calculating external and internal dose rates, following dispersion and deposition of radioactive materials in the atmosphere are described. Emphasis has been placed on analytical solutions that are appropriate for hand calculations. In addition, the methods for calculating dose rates from ingestion are discussed. A brief description of several computer programs are included for information on radionuclides. There has been no attempt to be comprehensive, and only a sampling of programs has been selected to illustrate the variety available

Radiation protection during decommissioning of the salt cavern Asse II. Recommendations by the German Commission on radiological protection; Strahlenschutz bei der Stilllegung der Schachtanlage Asse II. Empfehlung der Strahlenschutzkommission

Energy Technology Data Exchange (ETDEWEB)

NONE

2016-09-15

The recommendations by the German Commission on radiological protection concerning radiation protection during decommissioning of the salt cavern Asse II include the following issues: radiological consequences of non-controllable solution ingress, optional decommissioning modes, basis requirements of decommissioning, fact evaluation, determination of radiation exposure, radiological requirements for long-term safety, analysis of consequences and long-term safety demonstration, data and information, emergency protection, public transparency.

Foundations in radiological protection and radiotherapy

International Nuclear Information System (INIS)

Morales M, F.

2002-01-01

The work is divided in three parts. The part 1 are a brief abstrac of some important concepts related with the cells. The part 2 speak in general of the biological effects of the ionizing radiations according to the recommendations of the international commission of radiological protection. The part 3 refer to radiobiological calculations applying the quadratic lineal pattern to the radiotherapy. These calculations are important in view of the fact that they are applied for the introduction of new outlines of treatments

Goiania radiological accident: five years talking with the population

International Nuclear Information System (INIS)

Rozental, J.J.

1993-01-01

This article presents an overview five years after the Goiania radiological accident. It reviews from a number of important aspects the psychological impact and conflicting opinions, the public hearings and debates and, particularly describes the victims that still have difficulties to understand the accident and its consequences. (B.C.A.). 05 refs

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

International Nuclear Information System (INIS)

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

1985-08-01

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

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

International Nuclear Information System (INIS)

2006-01-01

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

Intercomparison of active personal dosemeters in interventional radiology

International Nuclear Information System (INIS)

Clairand, I.; Struelens, L.; Bordy, J. M.; Daures, J.; Debroas, J.; Denozieres, M.; Donadille, L.; Gouriou, J.; Itie, C.; Vaz, P.; D'Errico, F.

2008-01-01

The use of active personal dosemeters (APD) in interventional radiology was evaluated by Working Group 9 (Radiation protection dosimetry of medical staff) of the CONRAD project, which is a Coordination Action supported by the European Commission within its sixth Framework Programme. Interventional radiology procedures can be very complex and they can lead to relatively high doses to personnel who stand close to the primary radiation field and are mostly exposed to radiation scattered by the patient. For the adequate dosimetry of the scattered photons, APDs must be able to respond to low-energy [10-100 keV] and pulsed radiation with relatively high instantaneous dose rates. An intercomparison of five APD models deemed suitable for application in interventional radiology was organised in March 2007. The intercomparison used pulsed and continuous radiation beams, at CEA-LIST (Saclay (France)) and IRSN (Fontenay-aux-Roses (France)), respectively. A specific configuration, close to the clinical practice, was considered. The reference dose, in terms of Hp(10), was derived from air kerma measurements and from the measured and calculated energy distributions of the scattered radiation field. Additional Monte Carlo calculations were performed to investigate the energy spectra for different experimental conditions of the intercomparison. The results of this intercomparison are presented in this work and indicate which APDs are able to provide a correct response when used in the specific low-energy spectra and dose rates of pulsed X-rays encountered in interventional radiology. (authors)

Screening calculations for radioactive waste releases from non-nuclear facilities

International Nuclear Information System (INIS)

Xu, Shulan; Soederman, Ann-Louis

2009-02-01

A series of screening calculations have been performed to assess the potential radiological consequences of discharges of radioactive substances to the environment arising from waste from non-nuclear practices. Solid waste, as well as liquids that are not poured to the sewer, are incinerated and ashes from incineration and sludge from waste water treatment plants are disposed or reused at municipal disposal facilities. Airborne discharges refer to releases from an incineration facility and liquid discharges refer both to releases from hospitals and laboratories to the sewage system, as well as leakage from waste disposal facilities. The external exposure of workers is estimated both in the waste water treatment plant and at the disposal facility. The calculations follow the philosophy of the IAEA's safety guidance starting with a simple assessment based on very conservative assumptions which may be iteratively refined using progressively more complex models, with more realistic assumptions, as necessary. In the assessments of these types of disposal, with cautious assumptions, carried out in this report we conclude that the radiological impacts on representative individuals in the public are negligible in that they are small with respect to the target dose of 10 μSv/a. A Gaussian plume model was used to estimate the doses from airborne discharges from the incinerator and left a significant safety margin in the results considering the conservative assumptions in the calculations. For the sewage plant workers the realistic approach included a reduction in working hours and the shorter exposure time resulted in maximum doses around 10 μSv/a. The calculations for the waste disposal facility show that the doses are higher or in the range of the target dose. The excess for public exposure is mainly caused by H-3 and C-14. The assumption used in the calculation is that all of the radioactive substances sent to the incineration facility and waste water treatment plant

Screening calculations for radioactive waste releases from non-nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Shulan Xu; Soederman, Ann-Louis

2009-02-15

A series of screening calculations have been performed to assess the potential radiological consequences of discharges of radioactive substances to the environment arising from waste from non-nuclear practices. Solid waste, as well as liquids that are not poured to the sewer, are incinerated and ashes from incineration and sludge from waste water treatment plants are disposed or reused at municipal disposal facilities. Airborne discharges refer to releases from an incineration facility and liquid discharges refer both to releases from hospitals and laboratories to the sewage system, as well as leakage from waste disposal facilities. The external exposure of workers is estimated both in the waste water treatment plant and at the disposal facility. The calculations follow the philosophy of the IAEA's safety guidance starting with a simple assessment based on very conservative assumptions which may be iteratively refined using progressively more complex models, with more realistic assumptions, as necessary. In the assessments of these types of disposal, with cautious assumptions, carried out in this report we conclude that the radiological impacts on representative individuals in the public are negligible in that they are small with respect to the target dose of 10 muSv/a. A Gaussian plume model was used to estimate the doses from airborne discharges from the incinerator and left a significant safety margin in the results considering the conservative assumptions in the calculations. For the sewage plant workers the realistic approach included a reduction in working hours and the shorter exposure time resulted in maximum doses around 10 muSv/a. The calculations for the waste disposal facility show that the doses are higher or in the range of the target dose. The excess for public exposure is mainly caused by H-3 and C-14. The assumption used in the calculation is that all of the radioactive substances sent to the incineration facility and waste water treatment

Radiology fundamentals

CERN Document Server

Singh, Harjit

2011-01-01

""Radiology Fundamentals"" is a concise introduction to the dynamic field of radiology for medical students, non-radiology house staff, physician assistants, nurse practitioners, radiology assistants, and other allied health professionals. The goal of the book is to provide readers with general examples and brief discussions of basic radiographic principles and to serve as a curriculum guide, supplementing a radiology education and providing a solid foundation for further learning. Introductory chapters provide readers with the fundamental scientific concepts underlying the medical use of imag

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

Energy Technology Data Exchange (ETDEWEB)

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

2017-05-15

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

The radiological impact on the Greater London population of postulated accidental releases from the Sizewell PWR

CERN Document Server

Kelly, G N; Charles, D; Hemming, C R

1983-01-01

This report contains an assessment of the radiological impact on the Greater London population of postulated accidental releases from the Sizewell PWR. Three of the degraded core accident releases postulated by the CEGB are analysed. The consequences, conditional upon each release, are evaluated in terms of the health impact on the exposed population and the impact of countermeasures taken to limit the exposure. Consideration is given to the risk to the Greater London population as a whole and to individuals within it. The consequences are evaluated using the NRPB code MARC (Methodology for Assessing Radiological Consequences). The results presented in this report are all conditional upon the occurrence of each release. In assessing the significance of the results, due account must be taken of the frequency with which such releases may be predicted to occur.

Radiological assessment of past, present and potential sources to environmental contamination in the Southern Urals and strategies for remedial measures (SUCON)

Energy Technology Data Exchange (ETDEWEB)

Aarkrog, A. [Risoe National Lab. (Denmark); Simmonds, J. [National Radiological Protection Board (United Kingdom); Strand, P. [Norwegian Radiation Protection Authority (Norway); Christensen, G. [Institute of Energy Technology (Norway); Salbu, B. [Agricultural Univ. of Norway (Norway)

2000-12-01

This report summarises work done on the SUCON Project during 1996-1999 (European Commission Contract No. FI4C-CT95-0001). The project has focused on three major objectives: 1) An assessment of the radiological consequences of the contamination of the South Urals and the Ob river system from the production of plutonium at 'Mayak', 2) The development of models to calculate doses to individuals and populations in the South Urals using environmental data, and 3) The intercomparison, harmonisation and standardisation of techniques used in dose reconstruction and specification of good practice in particular with regard to remedial measures. (au)

Radiological assessment of past, present and potential sources to environmental contamination in the Southern Urals and strategies for remedial measures (SUCON)

International Nuclear Information System (INIS)

Aarkrog, A.; Simmonds, J.; Strand, P.; Christensen, G.; Salbu, B.

2000-12-01

This report summarises work done on the SUCON Project during 1996-1999 (European Commission Contract No. FI4C-CT95-0001). The project has focused on three major objectives: 1) An assessment of the radiological consequences of the contamination of the South Urals and the Ob river system from the production of plutonium at 'Mayak', 2) The development of models to calculate doses to individuals and populations in the South Urals using environmental data, and 3) The intercomparison, harmonisation and standardisation of techniques used in dose reconstruction and specification of good practice in particular with regard to remedial measures. (au)

Poul Erik Andersen's radiological work on Osteochondrodysplasias and interventional radiology

DEFF Research Database (Denmark)

Andersen, Poul Erik

2011-01-01

Hospital. His significant experience and extensive scientific work has led to many posts in the Danish Society of Interventional Radiology, the European Society of Radiology and the Cardiovascular and Interventional Radiological Society of Europe, where he is a fellow and has passed the European Board...... of Interventional Radiology - The European qualification in Interventional Radiology....

Sampling on radiological protection training in diagnostic radiology

International Nuclear Information System (INIS)

Gaona, E.

2001-01-01

Radiological security aspects were evaluated in radiology departments from Mexico City. The study was carried out in two stages, the first one evaluated 40 departments just before the implementation of the new Official Mexican Standards related to Radiological Security and Quality Control in Radiology; in the second stage 33 departments were evaluated 2 years after those standards were implanted, showing a favorable impact of the training programs for the type of answers obtained [es

Protective effect of lead aprons in medical radiology

International Nuclear Information System (INIS)

Huyskens, C.J.

1995-01-01

This article summarizes the results of an ongoing study regarding the protective effect that lead aprons, as used in medical radiology, have on the resulting effective dose for medical personnel. By means of model calculations we have analyzed the protection efficacy of lead aprons for various lead thicknesses, in function of tube potential and of variations in exposure geometry as they occur in practice. The degree of efficacy appears to be highly dependent on the fit of aprons because of the dominating influence of the equivalent dose of partially unshielded organs on the resulting effective dose. Also by model calculations we investigated the ratio between the effective dose and the operational quantify for personal dose monitoring. Our study enables the choice of appropriate correction factors for convering personal dosimetry measurements into effective dose, for typical exposure situations in medical radiology. (orig.) [de

Chronicle of pediatric radiology

International Nuclear Information System (INIS)

Benz-Bohm, Gabriele; Richter, Ernst

2012-01-01

The chronicle of pediatric radiology covers the following issues: Development of pediatric radiology in Germany (BRD, DDR, pediatric radiological accommodations); development of pediatric radiology in the Netherlands (chronology and pediatric radiological accommodations); development of pediatric radiology in Austria (chronology and pediatric radiological accommodations); development of pediatric radiology in Switzerland (chronology and pediatric radiological accommodations).

Socioeconomic consequences of nuclear reactor accidents

International Nuclear Information System (INIS)

Tawil, J.J.; Callaway, J.W.; Coles, B.L.; Cronin, F.J.; Currie, J.W.; Imhoff, K.L.; Lewis, P.M.; Nesse, R.J.; Strenge, D.L.

1984-06-01

This report identifies and characterizes the off-site socioeconomic consequences that would likely result from a severe radiological accident at a nuclear power plant. The types of impacts that are addressed include economic impacts, health impacts, social/psychological impacts and institutional impacts. These impacts are identified for each of several phases of a reactor accident - from the warning phase through the post-resettlement phase. The relative importance of the impact during each accident phase and the degree to which the impact can be predicted are indicated. The report also examines the methods that are currently used for assessing nuclear reactor accidents, including development of accident scenarios and the estimating of socioeconomic accident consequences with various models. Finally, a critical evaluation is made regarding the use of impact analyses in estimating the contribution of socioeconomic consequences to nuclear accident reactor accident risk. 116 references, 7 figures, 15 tables

Radiological Emergency Preparedness using Old ORTEC Whole Body Counter

International Nuclear Information System (INIS)

Badawy, W.M.

2012-01-01

During a radiological emergency (RE) a large number of occupational and public may be exposed externally and to a number of radionuclides internally as a result of inhalation or injection. The radiological effect is directly proportional to the time of exposure and the activity of the contaminant materials. The main task of this paper is to show the emergency preparedness capability of using the old ORTEC whole body counter (WBC). In case of a nuclear accident ORTEC WBC is ready for use to estimate the radioactivity which inhaled or digested with food, as well as in case of medical exposure in general and nuclear medicine in particular. The present study showed that the duration time to make analysis for only one individual is about 25 min. Hence 57 individuals are monitored per day. Consequently, old ORTEC WBC is effective tool in field of research and limited use for radiological and nuclear emergencies

Method for consequence calculations for severe accidents

International Nuclear Information System (INIS)

Nielsen, F.; Thykier-Nielsen, S.; Walmod-Larsen, O.

1986-08-01

This report was commissioned by the Swedish State Power Board, who wanted a method for calculation of radiation doses in the surroundings of nuclear power plants caused by severe accidents. The PLUCON4 code were used for the calculations. A TC-SV-accident at Ringhals 1 wer chosen as example. A transient without shutdown leads to core meltdown through the reactor vessel. The pressure peak at the moment of vessel failure opens a safety valve in the dry well. Meteorolgical data for two years from the Ringhals meteorological tower were analysed to find representative weather situations. As typical weather were chosen Pasquill D with wind speed 8 m/s, and as extreme weather were chosen Pasquill F with wind speed 4.8 m/s. (author)

Method for consequence calculations for severe accidents

International Nuclear Information System (INIS)

Nielsen, F.

1988-01-01

This report was commissioned by the Swedish State Power Board. The report contains a calculation of radiation doses in the surroundings caused by a theoretical core meltdown accident at Ringhals reactor No 3/4. The accident sequence chosen for the calcualtions was a release caused by total power failure. The calculations were made by means of the PLUCON4 code. A decontamination factor of 500 is used to account for the scrubber effect. Meteorological data for two years from the Ringhals meteorological tower were analysed to find representative weather situations. As typical weather, Pasquill D, was chosen with a wind speed of 10 m/s, and as extreme weather, Pasquill E, with a wind speed of 2 m/s. 19 refs. (author)

Weldon Spring dose calculations

International Nuclear Information System (INIS)

Dickson, H.W.; Hill, G.S.; Perdue, P.T.

1978-09-01

In response to a request by the Oak Ridge Operations (ORO) Office of the Department of Energy (DOE) for assistance to the Department of the Army (DA) on the decommissioning of the Weldon Spring Chemical Plant, the Health and Safety Research Division of the Oak Ridge National Laboratory (ORNL) performed limited dose assessment calculations for that site. Based upon radiological measurements from a number of soil samples analyzed by ORNL and from previously acquired radiological data for the Weldon Spring site, source terms were derived to calculate radiation doses for three specific site scenarios. These three hypothetical scenarios are: a wildlife refuge for hunting, fishing, and general outdoor recreation; a school with 40 hr per week occupancy by students and a custodian; and a truck farm producing fruits, vegetables, meat, and dairy products which may be consumed on site. Radiation doses are reported for each of these scenarios both for measured uranium daughter equilibrium ratios and for assumed secular equilibrium. Doses are lower for the nonequilibrium case

Imaging and radiology

Science.gov (United States)

Interventional radiology; Diagnostic radiology; X-ray imaging ... DIAGNOSTIC RADIOLOGY Diagnostic radiology helps health care professionals see structures inside your body. Doctors that specialize in the interpretation ...

Massive radiological releases profoundly differ from controlled releases

International Nuclear Information System (INIS)

Pascucci-Cahen, Ludivine; Patrick, Momal

2013-01-01

In this article, the authors report identification and assessment of different types of costs associated with nuclear accidents. They first outline that these cost assessments must be as exhaustive or comprehensive as possible. While referring to past accidents, they define the different categories of costs: on-site costs (decontamination and dismantling, electricity not produced on the site), off-site costs (health costs, psychological costs, farming losses), image-related costs (impact on food and farm product exports, decrease of other exports), costs related to energy production, costs related to contaminated areas (refugees, lands). They give an assessment of a severe nuclear accident (i.e. an accident with important but controlled radiological releases) in France and outline that it would be a national catastrophe which could be however managed. They discuss the possible variations of the estimated costs. Then, they show that a major accident (i.e. an accident with massive radiological releases) in France would be an unmanageable European catastrophe because of the radiological consequences, of high economic costs, and of huge losses

Contribution to the calculation of the alpha value in the study of optimization on radiological protection

International Nuclear Information System (INIS)

Perez, Clarice de Freitas Acosta

2007-01-01

The Alpha value is an extremely important criterion because it determines the time that each country takes to reach its proposals to decrease the doses to workers involved with ionizing radiation sources. Presently, countries adopt a single value for alpha based in the annual gross national product, GNP, per capita. The aim of this paper is to show that it should be more efficient the selection of a curve for alpha in place of a single value. This curve, in its turn, should allow an alpha value that would be constraint to the greatest individual doses present in each optimization process, applied to design and operation. These maximum individual doses should represent the dose distribution between the workers team. To build the curve, alpha values suggested will not be based on the GNP per capita but on a distribution function of the maximum individual doses and on the time necessary to reach the goal of 1/10 of the annual dose limit, that is, to reach the region where the individual doses are considered acceptable. This new alpha value approach solves several problems risen by the present methodology, among which we emphasize: a) It can be accomplished only one optimization for each radiological protection option set; b) each country may have different constraints limits that can create serious problems in the international interchange; c) it avoids the possibility to calculate the probable death rate due to the collective dose. This type of calculation is undesirable to international organization. (author)

Dosimetry in Interventional Radiology - Effective Dose Estimation

International Nuclear Information System (INIS)

Miljanic, S.; Buls, N.; Clerinx, P.; Jarvinen, H.; Nikodemova, D.; Ranogajec-Komor, M; D'Errico, F.

2008-01-01

Interventional radiological procedures can lead to significant radiation doses to patients and to staff members. In order to evaluate the personal doses with respect to the regulatory dose limits, doses measured by dosimeters have to be converted to effective doses (E). Measurement of personal dose equivalent Hp(10) using a single unshielded dosimeter above the lead apron can lead to significant overestimation of the effective dose, while the measurement with dosimeter under the apron can lead to underestimation. To improve the accuracy, measurements with two dosimeters, one above and the other under the apron have been suggested ( d ouble dosimetry ) . The ICRP has recommended that interventional radiology departments develop a policy that staff should wear two dosimeters. The aim of this study was to review the double dosimetry algorithms for the calculation of effective dose in high dose interventional radiology procedures. The results will be used to develop general guidelines for personal dosimetry in interventional radiology procedures. This work has been carried out by Working Group 9 (Radiation protection dosimetry of medical staff) of the CONRAD project, which is a Coordination Action supported by the European Commission within its 6th Framework Program.(author)

Model review and evaluation for application in DOE safety basis documentation of chemical accidents - modeling guidance for atmospheric dispersion and consequence assessment

Energy Technology Data Exchange (ETDEWEB)

Lazaro, M. A. [Argonne National Lab. (ANL), Argonne, IL (United States); Woodarad, K. [Argonne National Lab. (ANL), Argonne, IL (United States); Hanna, S. R. [Argonne National Lab. (ANL), Argonne, IL (United States); Hesse, D. J. [Argonne National Lab. (ANL), Argonne, IL (United States); Huang, J. -C. [Argonne National Lab. (ANL), Argonne, IL (United States); Lewis, J. [Argonne National Lab. (ANL), Argonne, IL (United States); Mazzola, C. A. [Argonne National Lab. (ANL), Argonne, IL (United States)

1997-09-01

The U.S. Department of Energy (DOE), through its Defense Programs (DP), Office of Engineering and Operations Suppon, established the Accident Phenomenology and Consequence (AP AC) Methodology Evaluation Program to identify and evaluate methodologies and computer codes to support accident phenomenological and consequence calculations for both radiological and nonradiological materials at DOE facilities and to identify development needs. The program is also intended to define and recommend "best or good engineering/safety analysis practices" to be followed in preparing ''design or beyond design basis" assessments to be included in DOE nuclear and nonnuclear facility safety documents. The AP AC effort is intended to provide scientifically sound and more consistent analytical approaches, by identifying model selection procedures and application methodologies, in order to enhance safety analysis activities throughout the DOE complex.

Radiological consequences of atmospheric releases from coal-fired power plants

International Nuclear Information System (INIS)

Tveten, U.

1985-06-01

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

Convention on assistance in the case of a nuclear accident or radiological emergency

International Nuclear Information System (INIS)

1986-11-01

The full text of the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency adopted by the General Conference at its special session from 24-26 September 1986 is presented. It is stipulated that the States Parties shall cooperate between themselves and with the Agency to facilitate prompt assistance in the event of a nuclear accident or radiological emergency to minimize its consequences and to protect life, the property and the environment from the effects of radioactive releases

Radiological Control Manual

Energy Technology Data Exchange (ETDEWEB)

1993-04-01

This manual has been prepared by Lawrence Berkeley Laboratory to provide guidance for site-specific additions, supplements, and clarifications to the DOE Radiological Control Manual. The guidance provided in this manual is based on the requirements given in Title 10 Code of Federal Regulations Part 835, Radiation Protection for Occupational Workers, DOE Order 5480.11, Radiation Protection for Occupational Workers, and the DOE Radiological Control Manual. The topics covered are (1) excellence in radiological control, (2) radiological standards, (3) conduct of radiological work, (4) radioactive materials, (5) radiological health support operations, (6) training and qualification, and (7) radiological records.

Radiological Control Manual

International Nuclear Information System (INIS)

1993-04-01

This manual has been prepared by Lawrence Berkeley Laboratory to provide guidance for site-specific additions, supplements, and clarifications to the DOE Radiological Control Manual. The guidance provided in this manual is based on the requirements given in Title 10 Code of Federal Regulations Part 835, Radiation Protection for Occupational Workers, DOE Order 5480.11, Radiation Protection for Occupational Workers, and the DOE Radiological Control Manual. The topics covered are (1) excellence in radiological control, (2) radiological standards, (3) conduct of radiological work, (4) radioactive materials, (5) radiological health support operations, (6) training and qualification, and (7) radiological records

Radioactive Waste Management Complex low-level waste radiological performance assessment

Energy Technology Data Exchange (ETDEWEB)

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

1994-04-01

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

Radioactive Waste Management Complex low-level waste radiological performance assessment

International Nuclear Information System (INIS)

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

1994-04-01

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

Radiological English

Energy Technology Data Exchange (ETDEWEB)

Ribes, R. [Hospital Reina Sofia, Cordoba (Spain). Servicio de Radiologia; Ros, P.R. [Harvard Medical School, Boston, MA (United States). Div. of Radiology

2007-07-01

The book is an introductory book to radiological English on the basis that there are a lot of radiologists, radiology residents, radiology nurses, radiology students, and radiographers worldwide whose English level is indeterminate because their reading skills are much higher than their fluency. It is intended to help those health care professionals who need English for their work but do not speak English on a day-to-day basis. (orig.)

Radiological English

International Nuclear Information System (INIS)

Ribes, R.; Ros, P.R.

2007-01-01

The book is an introductory book to radiological English on the basis that there are a lot of radiologists, radiology residents, radiology nurses, radiology students, and radiographers worldwide whose English level is indeterminate because their reading skills are much higher than their fluency. It is intended to help those health care professionals who need English for their work but do not speak English on a day-to-day basis. (orig.)

Handbook of radiologic procedures

International Nuclear Information System (INIS)

Hedgcock, M.

1986-01-01

This book is organized around radiologic procedures with each discussed from the points of view of: indications, contraindications, materials, method of procedures and complications. Covered in this book are: emergency radiology chest radiology, bone radiology, gastrointestinal radiology, GU radiology, pediatric radiology, computerized tomography, neuroradiology, visceral and peripheral angiography, cardiovascular radiology, nuclear medicine, lymphangiography, and mammography

Advantages and Disadvantages in Image Processing with Free Software in Radiology.

Science.gov (United States)

Mujika, Katrin Muradas; Méndez, Juan Antonio Juanes; de Miguel, Andrés Framiñan

2018-01-15

Currently, there are sophisticated applications that make it possible to visualize medical images and even to manipulate them. These software applications are of great interest, both from a teaching and a radiological perspective. In addition, some of these applications are known as Free Open Source Software because they are free and the source code is freely available, and therefore it can be easily obtained even on personal computers. Two examples of free open source software are Osirix Lite® and 3D Slicer®. However, this last group of free applications have limitations in its use. For the radiological field, manipulating and post-processing images is increasingly important. Consequently, sophisticated computing tools that combine software and hardware to process medical images are needed. In radiology, graphic workstations allow their users to process, review, analyse, communicate and exchange multidimensional digital images acquired with different image-capturing radiological devices. These radiological devices are basically CT (Computerised Tomography), MRI (Magnetic Resonance Imaging), PET (Positron Emission Tomography), etc. Nevertheless, the programs included in these workstations have a high cost which always depends on the software provider and is always subject to its norms and requirements. With this study, we aim to present the advantages and disadvantages of these radiological image visualization systems in the advanced management of radiological studies. We will compare the features of the VITREA2® and AW VolumeShare 5® radiology workstation with free open source software applications like OsiriX® and 3D Slicer®, with examples from specific studies.

Planning the medical response to radiological accidents

International Nuclear Information System (INIS)

1998-01-01

Radioactive substances and other sources of ionizing radiation are used to assist in diagnosing and treating diseases, improving agricultural yields, producing electricity and expanding scientific knowledge. The application of sources of radiation is growing daily, and consequently the need to plan for radiological accidents is growing. While the risk of such accidents cannot be entirely eliminated, experience shows that most of the rare cases that have occurred could have been prevented, as they are often caused by human error. Recent radiological accidents such as those at Chernobyl (Ukraine 1986), Goiania (Brazil 1987), San Salvador (El Salvador 1989), Sor-Van (Israel 1990), Hanoi (Viet Nam 1992) and Tammiku (Estonia 1994) have demonstrated the importance of adequate preparation for dealing with such emergencies. Medical preparedness for radiological accidents must be considered an integral part of general emergency planning and preparedness and established within the national framework for radiation protection and safety. An IAEA Technical Committee meeting held in Istanbul in 1988 produced some initial guidance on the subject, which was subsequently developed, reviewed and updated by groups of consultants in 1989, 1992 and 1996. Special comments were provided by WHO, as co-sponsor of this publication, in 1997. This Safety Report outlines the roles and tasks of health authorities and hospital administrators in emergency preparedness for radiological accidents. Health authorities may use this document as the basis for their medical management in a radiological emergency, bearing in mind that adaptations will almost certainly be necessary to take into account the local conditions. This publication also provides information relevant to the integration of medical preparedness into emergency plans

RSVP radiology

International Nuclear Information System (INIS)

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

1990-01-01

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

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

International Nuclear Information System (INIS)

Hill, M.D.

1979-06-01

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

Radiological anatomy - evaluation of integrative education in radiology.

Science.gov (United States)

Dettmer, S; Schmiedl, A; Meyer, S; Giesemann, A; Pabst, R; Weidemann, J; Wacker, F K; Kirchhoff, T

2013-09-01

Evaluation and analysis of the integrative course "Radiological Anatomy" established since 2007 at the Medical School Hannover (MHH) in comparison with conventional education. Anatomy and radiology are usually taught separately with a considerable time lag. Interdisciplinary teaching of these associated subjects seems logical for several reasons. Therefore, the integrative course "Radiological Anatomy" was established in the second year of medical education, combining these two closely related subjects. This interdisciplinary course was retrospectively evaluated by consideration of a student questionnaire and staff observations. The advantages and disadvantages of integrative teaching in medical education are discussed. The course ratings were excellent (median 1; mean 1.3 on a scale of 1 to 6). This is significantly (p radiology increased during the course (88 %). According to the students' suggestions the course was enhanced by a visitation in the Department of Radiology and the additional topic central nervous system. Integrative teaching of anatomy and radiology was well received by the students. Both, anatomical and radiological comprehension and the motivation to learn were improved. However, it should be considered, that the amount of work and time required by the teaching staff is considerably increased compared to traditional teaching. © Georg Thieme Verlag KG Stuttgart · New York.

Analysis of the Radiology Reports from Radiology Clinics

International Nuclear Information System (INIS)

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

2009-01-01

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

Automated Calibration of Dosimeters for Diagnostic Radiology

International Nuclear Information System (INIS)

Romero Acosta, A.; Gutierrez Lores, S.

2015-01-01

Calibration of dosimeters for diagnostic radiology includes current and charge measurements, which are often repetitive. However, these measurements are usually done using modern electrometers, which are equipped with an RS-232 interface that enables instrument control from a computer. This paper presents an automated system aimed to the measurements for the calibration of dosimeters used in diagnostic radiology. A software application was developed, in order to achieve the acquisition of the electric charge readings, measured values of the monitor chamber, calculation of the calibration coefficient and issue of a calibration certificate. A primary data record file is filled and stored in the computer hard disk. The calibration method used was calibration by substitution. With this system, a better control over the calibration process is achieved and the need for human intervention is reduced. the automated system will be used in the calibration of dosimeters for diagnostic radiology at the Cuban Secondary Standard Dosimetry Laboratory of the Center for Radiation Protection and Hygiene. (Author)

Dosimetry in diagnosis examinations in radiology. S.F.P.M. Report No. 30, December 2014

International Nuclear Information System (INIS)

Defez, Didier; Dreuil, Serge; Hapdey, Sebastien; Leleu, Cyril; Demonchy, Mathilde; Jarrige, Valerie; Le Rouzic, Gilles; Dedieu, Veronique; Ferrrer, Ludovic; Guillhem, Marie-Therese; Meyer, Philippe; Simon, Luc

2014-12-01

This document is an update of the SFPM report No. 21 from 2004. It aims at helping the professionals involved in radiology when assessing the delivered doses to patients during conventional radiology examinations, in mammography and scanography. The first part recalls all the dosimetric data susceptible to characterize the X ray beam, the patient exposure and the radiological risk. The second part addresses the different types of sensors which can be used to obtain the different measurable dosimetric values. The third part presents the calculation, analytical and numerical methods. The fourth part proposes a set of sheets of data to be acquired on an installation to perform a measurement and/or a dose calculation

Investigation of possible methods for equipment self-tests in digital radiology

International Nuclear Information System (INIS)

Zoetelief, J.; Idris, H. H. E.; Jansen, J. T. M.

2005-01-01

Quality control in digital radiology can be time-consuming. Equipment self-tests may significantly decrease staff workload. The two most essential parameters for radiology systems are image quality and patient dose. Concerning patient dose, information on the dose-area product (DAP) values generally forms the basis for assessment of patient dose. DAP-values can be measured using a transmission ionisation chamber or calculated from equipment settings. In the present study, various image quality parameters were derived using a contrast-detail (C-D) phantom. The investigation included a computer-aided assessment of C-D images, which produced various parameters, and also parameters based upon scoring by human observers. In addition, another parameter was calculated from modulation transfer function (MTF) measurements. The automatically calculated parameters showed good correlation with human readings, although the number of X-ray systems studied is still limited. We propose a combined evaluation of DAP and automatically calculated C-D or MTF parameters for equipment self-tests. (authors)

Fundamentals for cost calculations of X-ray equipment

International Nuclear Information System (INIS)

Bossard, F.

1985-01-01

Economic implications of running an X-ray departement in Switzerland will be illustrated by comparing operating costs of private radiological institutes with and without CT to the operating costs of large radiological departments in hospitals with and without CT and to the operating costs of simple X-ray equipment in general practicioners' offices. - These costs calculations form the basis for cost-benefit analyses. (orig.) [de

Development of an anthropomorphic model and a Monte Carlo calculation code devoted to the physical reconstruction of a radiological accident

International Nuclear Information System (INIS)

Roux, A.

2001-01-01

The diversity of radiological accidents makes difficult the medical prognosis and the therapy choice from only clinical observations. To complete this information, it is important to know the global dose received by the organism and the dose distributions in depth in tissues. The dose estimation can be made by a physical reconstruction of the accident with the help of tools based on experimental techniques or on calculation. The software of the geometry construction (M.G.E.D.), associated to the Monte-Carlo code of photons and neutrons transport (M.O.R.S.E.) replies these constraints. An important result of this work is to determine the principal parameters to know in function of the accident type, as well as the precision level required for these parameters. (N.C.)

A parametric study of MELCOR Accident Consequence Code System 2 (MACCS2) Input Values for the Predicted Health Effect

International Nuclear Information System (INIS)

Kim, So Ra; Min, Byung Il; Park, Ki Hyun; Yang, Byung Mo; Suh, Kyung Suk

2016-01-01

The MELCOR Accident Consequence Code System 2, MACCS2, has been the most widely used through the world among the off-site consequence analysis codes. MACCS2 code is used to estimate the radionuclide concentrations, radiological doses, health effects, and economic consequences that could result from the hypothetical nuclear accidents. Most of the MACCS model parameter values are defined by the user and those input parameters can make a significant impact on the output. A limited parametric study was performed to identify the relative importance of the values of each input parameters in determining the predicted early and latent health effects in MACCS2. These results would not be applicable to every case of the nuclear accidents, because only the limited calculation was performed with Kori-specific data. The endpoints of the assessment were early- and latent cancer-risk in the exposed population, therefore it might produce the different results with the parametric studies for other endpoints, such as contamination level, absorbed dose, and economic cost. Accident consequence assessment is important for decision making to minimize the health effect from radiation exposure, accordingly the sufficient parametric studies are required for the various endpoints and input parameters in further research

Design basis event consequence analyses for the Yucca Mountain project

International Nuclear Information System (INIS)

Orvis, D.D.; Haas, M.N.; Martin, J.H.

1997-01-01

Design basis event (DBE) definition and analysis is an ongoing and integrated activity among the design and analysis groups of the Yucca Mountain Project (YMP). DBE's are those that potentially lead to breach of the waste package and waste form (e.g., spent fuel rods) with consequent release of radionuclides to the environment. A Preliminary Hazards Analysis (PHA) provided a systematic screening of external and internal events that were candidate DBE's that will be subjected to analyses for radiological consequences. As preparation, pilot consequence analyses for the repository subsurface and surface facilities have been performed to define the methodology, data requirements, and applicable regulatory limits

Proposed radiological protection rules for patients in radiodiagnostics

International Nuclear Information System (INIS)

Yacovenco, A.; Souza, A.C.A.; Ferreira, R.S.

1998-01-01

Faced with the increasing exposure of the population to ionizing radiations and the need to respect users' rights, political and scientific efforts have been undertaken in order to improve image quality in radiodiagnostics and reduce risks to patients. In Brazil, in the past 20 years, a low rate of investment in this area and inadequate health policies have lead to diagnostic radiology services of poor quality. For their part, scientific societies, professional associations and the Ministry of Health have issued federal and state norms which require the control of physical parameters of the radiological equipment. Consequently, there is a need to create a National Reference Laboratory to oversee, inspect and evaluate the implementation of such norms. Another topic addressed in this article is the professional profile of the Medical Physics Specialist. (author)

Reconstructive dosimetry of radiological accidents - a brazilian case study of industrial gammagraphy

International Nuclear Information System (INIS)

Silva, Francisco Cesar Augusto da; Hunt, John G.; Ramalho, Adriana; Pinto, Livia M.F. Amalfi

2001-01-01

In may 2000, an operator of industrial gammagraphy, during a work of maintenance of a cobalt source irradiator, suffered a radiological accident which caused serious consequences for its left hand. Specialists who work in the Group of Overexposure Analysis (GADE/IRD/CNEN), began the reconstructive dosimetry for estimate the radiation dose. The objective was to determine the real dose received by the operator and to make possible the medical evaluation and to prescribe the medical procedures for the involved victim's treatment. This work presents the reconstructive dosimetry done by theoretical, experimental and computation methods for determining the radiation doses of the operator. Related to the computation method a program was used for external dose calculation based on Monte Carlo's Method and a human body simulator composed by voxels. It is also showed values of the effective and equivalent doses that caused serious lesions in the operator's hand. (author)

RadCon: A Radiological Consequences Model

International Nuclear Information System (INIS)

Crawford, J.; Domel, R.U.

2000-05-01

RadCon estimates the dose received by user selected groups in the population from an accidental release of radionuclides to the environment. The exposure pathways considered are external exposure from the cloud and ground and internal exposure from inhalation and ingestion of contaminated food. Atmospheric dispersion modelling is carried out externally to RadCon.Given a two dimensional time varying air and ground concentration of radioactive elements, RadCon allows the user to: view the air and ground concentration over the affected area, select optional parameters and calculate the dose to people,display the results to the user, and change the parameter values. RadCon offers two user interfaces: 1) the standard graphical user interface which is started using Java DoseApp at the command line, or by setting up a shortcut to this command (particularly when RadCon is installed on a PC) and 2) the text based interface used to generate information for the model inter-comparison exercise . This is initiated using Java BIOMASS at the command line, or an equivalent shortcut. The text based interface was developed for research purposes and is not generally available. Appendices A, B and C provide a summary of instructions on setting up RadCon. This will generally be carried out by the computer support personnel

Radiology research in mainland China in the past 10 years: a survey of original articles published in Radiology and European Radiology.

Science.gov (United States)

Zhang, Long Jiang; Wang, Yun Fei; Yang, Zhen Lu; Schoepf, U Joseph; Xu, Jiaqian; Lu, Guang Ming; Li, Enzhong

2017-10-01

To evaluate the features and trends of Radiology research in Mainland China through bibliometric analysis of the original articles published in Radiology and European Radiology (ER) between 2006 and 2015. We reviewed the original articles published in Radiology and ER between 2006 and 2015. The following information was abstracted: imaging subspecialty, imaging technique(s) used, research type, sample size, study design, statistical analysis, study results, funding declarations, international collaborations, number of authors, department and province of the first author. All variables were examined longitudinally over time. Radiology research in Mainland China saw a substantial increase in original research articles published, especially in the last 5 years (P Radiology research, neuroradiology, vascular/interventional Radiology, and abdominal Radiology were the most productive fields; MR imaging was the most used modality, and a distinct geographic provenience was observed for articles published in Radiology and ER. Radiology research in Mainland China has seen substantial growth in the past 5 years with neuroradiology, vascular/interventional Radiology, and abdominal Radiology as the most productive fields. MR imaging is the most used modality. Article provenience shows a distinct geographical pattern. • Radiology research in Mainland China saw a substantial increase. • Neuroradiology, vascular/interventional Radiology, and abdominal Radiology are the most productive fields. • MRI is the most used modality in Mainland China's Radiology research. • Guangdong, Shanghai, and Beijing are the most productive provinces.

Use and experience of radiological evaluation tools for the early phase during nuclear emergency exercises in Belgium

International Nuclear Information System (INIS)

Sohier, A.; Ruts, J.; Hardeman, F.

2003-01-01

end-points of interest, such doses, instantaneous and time integrated air concentrations and depositions. Real-time information is provided by stack monitoring and local meteorological instrumentation. At any moment the module can switch to 'prevision mode' under which the consequences of expected or possible future releases can be assessed, allowing simulating what-if situations. In the prevision mode avertable as well as total quantities (doses) are calculated. A very useful feature of the tool is the 'Standard Scenario' mode to be used prior to any release providing guidance upon precautionary intervention measures. Under guidance of Electrabel a comprehensive set of predefined accident scenarios for the main installations has been defined and introduced in a database of the tool. The accident scenarios are classified according to key events (such as rupture of primary circuit with or without core melt, steam generator pipe breaches, etc) and the status of mitigating equipment (such as penetrations, sprays, filters etc). Altogether more than 100 scenarios per unit have been defined, each yielding a specific source term. Answering a series of questions put in a logic scheme (a 'logigramme') about the status of the installation, the operator is guided towards the selection of the most appropriate scenario. This mode is very simple to use, with very little probability of making mistakes, and it provides results of radiological consequences almost instantaneously. In practice, the tool is installed both at the nuclear site and in the crisis centre. Results of calculations are transferred by modem from the site to the evaluation cell where the results can be presented in a very flexible way to the evaluation team, and where all underlying assumptions of each assessment are automatically available. (author)

Estimated consequences from severe spent nuclear fuel transportation accidents

International Nuclear Information System (INIS)

Arnish, J.J.; Monette, F.; LePoire, D.; Biwer, B.M.

1996-01-01

The RISKIND software package is used to estimate radiological consequences of severe accident scenarios involving the transportation of spent nuclear fuel. Radiological risks are estimated for both a collective population and a maximally exposed individual based on representative truck and rail cask designs described in the U.S. Nuclear Regulatory Commission (NRC) modal study. The estimate of collective population risk considers all possible environmental pathways, including acute and long-term exposures, and is presented in terms of the 50-y committed effective dose equivalent. Radiological risks to a maximally exposed individual from acute exposure are estimated and presented in terms of the first year and 50-y committed effective dose equivalent. Consequences are estimated for accidents occurring in rural and urban population areas. The modeled pathways include inhalation during initial passing of the radioactive cloud, external exposure from a reduction of the cask shielding, long-term external exposure. from ground deposition, and ingestion from contaminated food (rural only). The major pathways and contributing radionuclides are identified, and the effects of possible mitigative actions are discussed. The cask accident responses and the radionuclide release fractions are modeled as described in the NRC modal study. Estimates of severe accident probabilities are presented for both truck and rail modes of transport. The assumptions made in this study tend to be conservative; however, a set of multiplicative factors are identified that can be applied to estimate more realistic conditions

Recommendations guide in radiological accidents for first respondents, firemen and policemen

International Nuclear Information System (INIS)

Astudillo, A. J.; Ambriz, J. J.; Paredes, L. C.

2011-10-01

The action guides for the primary task forces of the Firemen Corps and the Public Security Elements, before the presence of radiological accidents are presented. The objective of these guides is to give the recommendations for the initial response to the emergency that fulfills the following criterions: to to Apply with readiness all the reasonable measures to protect the victims and the public, in order to minimizing the radiological and non radiological effects to the health; b) to Retrieve the control of the situation and to mitigate the consequences; c) to Protect the emergency personnel during the response operations; d) to Compile and to protect the information that can be useful to treat the effects to the health, of the victims and public in general, and to prevent that emergencies seemed are repeat in the future; e) to Create and to maintain the public's trust in the response; f) to Establish a base for an action of lingering response, and to Suggest evaluation criterions of the radiological emergency, the organization criterions, operation and surrounding of the emergency area. (Author)

Radiological differential diagnosis of rheumatoid arthritis; Radiologische Differenzialdiagnose der rheumatoiden Arthritis

Energy Technology Data Exchange (ETDEWEB)

Wick, M.C.; Klauser, A.S. [Medizinische Universitaet Innsbruck, Department Radiologie, Innsbruck (Austria)

2012-02-15

Establishing an early and reliable diagnosis of rheumatoid arthritis (RA) is of major importance but can be a great clinical challenge leading to direct therapeutic consequences. No single epidemiological, genetic, clinical, serological or radiological test exists which can exclusively diagnose RA. In general diagnosis of RA includes a case history, clinical signs, laboratory abnormalities and radiological examinations, viz. conventional radiography of the joints of the hands and feet. This review summarizes the most important radiological features of RA and the radiological findings of its closest differential diagnoses. (orig.) [German] Eine fruehe Diagnosestellung bei rheumatoider Arthritis (RA) stellt eine grosse klinische Herausforderung dar, da sich daraus unmittelbare therapeutische Konsequenzen ableiten. Es gibt keinen epidemiologischen, genetischen, klinischen, serologischen oder radiologischen Test, mit dessen alleiniger Anwendung die Diagnose der RA definitiv gestellt werden kann. Die Diagnose der RA erfolgt durch die Kombination von Patientenanamnese, klinischen Zeichen und serologischen Biomarkern in Zusammenschau mit der radiologischen Diagnostik, allen voran der Anwendung konventioneller Roentgenbilder der Haende und Fuesse. In diesem Uebersichtsartikel werden die wichtigsten radiologischen Merkmale zur Diagnose der RA und der diagnostisch haeufigsten Differenzialerkrankungen dargestellt. (orig.)

Health and safety consequences of medical isotope processing at the Hanford Site 325 building

Energy Technology Data Exchange (ETDEWEB)

Nielsen, D. L.

1997-11-19

Potential activities associated with medical isotope processing at the Hanford Site 325 Building laboratory and hot cell facilities are evaluated to assess the health and safety consequences if these activities are to be implemented as part of a combined tritium and medical isotope production mission for the Fast Flux Text Facility (FFTF). The types of activities included in this analysis are unloading irradiated isotope production assemblies at the 325 Building, recovery and dissolution of the target materials, separation of the product isotopes as required, and preparation of the isotopes for shipment to commercial distributors who supply isotopes to the medical conunuriity. Possible consequences to members of the public and to workers from both radiological and non-radiological hazards are considered in this evaluation. Section 2 of this docinnent describes the assumptions and methods used for the health and safety consequences analysis, section 3 presents the results of the analysis, and section 4 summarizes the results and conclusions from the analysis.

Civil liability for nuclear and radiological damage

International Nuclear Information System (INIS)

Puig, D.

2001-10-01

The present work gives details of the nuclear damage, the accidents of Chernobil, three Mile Inland and Tokaimura with their respective legal consequences, the nature of the responsibility and bases for their establishment, conventions about civil responsibility for nuclear damages to regional and world level as well as other condition of conventions of the Ibero-American countries with regard to the approval of the conventions it has more than enough civil responsibility for nuclear and radiological accident damages

Radiological protection and environmental management

International Nuclear Information System (INIS)

Perez Fonseca, A.

2010-01-01

From the beginning of its industrial activity twenty five years ago, the Juzbado Factory of Enusa Group has always upheld a strong commitment with Radiological Protection and environmental respect and protection. Consequently, the evolution of dose shows a downward trend over the years. Although production has been increased gradually, the average doses to workers have stayed below 1 mSv. In order to identify and prevent the potential environmental impacts of its industrial activity and minimize its impact on the surroundings, the facility develops and environmental management system according to UNE-EN-ISO 14001 since 1999. (Author)

Calculation of health risks from spent-nuclear-fuel transportation accidents

International Nuclear Information System (INIS)

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

1987-01-01

Models developed to analyze potential radiological health risks from various accident scenarios during transportation of spent nuclear fuels are described. The models are designed both for detailed route-specific risk analyses and for use in conducting overall risk analyses for route selection and related decision-making activities. The radiological risks calculated include individual dose commitments, collective dose commitments, and long-term (100-year) environmental dose commitments to a population following release of radioactivity. To facilitate route-specific analysis, a state-level database was developed and incorporated into the model. Route-specific analysis is demonstrated by the calculation of radiological risks resulting from various accident scenarios, as postulated by the recent US Nuclear Regulatory Commission Modal Study, for four representative states selected from various regions of the United States. 10 refs., 3 figs., 3 tabs

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.)

Software for the estimation of foetal radiation dose to patients and staff in diagnostic radiology

Energy Technology Data Exchange (ETDEWEB)

Osei, E K [Department of Radiation Physics, Princess Margaret Hospital, 610 University Avenue, Toronto ON M5G 2M9 (Canada); Darko, J B [Department of Radiation Physics, Princess Margaret Hospital, 610 University Avenue, Toronto ON M5G 2M9 (Canada); Faulkner, K [Quality Assurance Centre, Newcastle General Hospital, Westgate Road, Newcastle Upon Tyne NE4 6BE (United Kingdom); Kotre, C J [Regional Medical Physics Department, Newcastle General Hospital, Westgate Road, Newcastle Upon Tyne NE4 6BE (United Kingdom)

2003-06-01

Occasionally, it is clinically necessary to perform a radiological examination(s) on a woman who is known to be pregnant or an examination is performed on a woman who subsequently discovers that she was pregnant at the time. In radiological examinations, especially of the lower abdomen and pelvis area, the foetus is directly irradiated. It is therefore important to be able to determine the absorbed dose to the foetus in diagnostic radiology for pregnant patients as well as the foetal dose from occupational exposure of the pregnant worker. The determination of the absorbed dose to the unborn child in diagnostic radiology is of interest as a basis for risk estimates from medical exposure of the pregnant patient and occupational exposure of the pregnant worker. In this paper we describe a simple computer program, FetDose, which calculates the dose to the foetus from both medical and occupational exposures of the pregnant woman. It also calculates the risks of in utero exposure, compares calculated doses with published data in the literature and provides information on the natural spontaneous risks. The program will be a useful tool for the medical and paramedical personnel who are involved with foetal dose (and hence risks) calculations and counselling of pregnant women who may be concerned about in utero exposure of their foetuses.

Software for the estimation of foetal radiation dose to patients and staff in diagnostic radiology

International Nuclear Information System (INIS)

Osei, E K; Darko, J B; Faulkner, K; Kotre, C J

2003-01-01

Occasionally, it is clinically necessary to perform a radiological examination(s) on a woman who is known to be pregnant or an examination is performed on a woman who subsequently discovers that she was pregnant at the time. In radiological examinations, especially of the lower abdomen and pelvis area, the foetus is directly irradiated. It is therefore important to be able to determine the absorbed dose to the foetus in diagnostic radiology for pregnant patients as well as the foetal dose from occupational exposure of the pregnant worker. The determination of the absorbed dose to the unborn child in diagnostic radiology is of interest as a basis for risk estimates from medical exposure of the pregnant patient and occupational exposure of the pregnant worker. In this paper we describe a simple computer program, FetDose, which calculates the dose to the foetus from both medical and occupational exposures of the pregnant woman. It also calculates the risks of in utero exposure, compares calculated doses with published data in the literature and provides information on the natural spontaneous risks. The program will be a useful tool for the medical and paramedical personnel who are involved with foetal dose (and hence risks) calculations and counselling of pregnant women who may be concerned about in utero exposure of their foetuses

Determination of the radiological capacity in the IEA environment

International Nuclear Information System (INIS)

Palacios, E.; Oliveira, P.L.C.

1976-01-01

The radiological capacity in the IEA environment, was calculated according to the recommendations of the International Commission on Radiological Protection, in order to assess the management wastes disposal programming. The value of radiological capacity, take into account the isotopic composition, at the production moment, was 850 Ci/year. The IEA radioactive environment disposal, up to now, employed just a small fraction of its capacity. Iodine I-131 air inhalation, and external radiation, derivated from the sediments around the discharged point of Pinheiros river, were the 'critical pathways'; for the second case the 'critical radionuclides' were: Te-125m, Te-123m, Te-127m, I-131 e Cs-137. The 'Dose Commitment' of one year operation will be not upper than 20 mrad in the infant's thyroid and 140 mrad in the whole body [pt

Economic evaluation of angiographic interventions including a whole-radiology in- and outpatient care

International Nuclear Information System (INIS)

Nolte-Ernsting, C.; Abel, K.; Krupski, G.; Lorenzen, J.; Adam, G.

2006-01-01

Purpose: To determine the economic efficiency of a whole-radiology in- and outpatient treatment with angiographic interventions performed as the main or sole therapy. Materials and Methods: The calculations represent the data of a university radiology department, including the following angiographic interventions (neuroradiology not considered): Vascular intervention (PTA, stent implantation) of kidneys and extremities, recanalization of hemodialysis access, chemoembolization, diagnostic arterioportal liver CT, port implantation, varicocele embolization, PTCD, percutaneous implantation of biliary stent. First, the different angiographic interventions are categorized with reference to the German DRG system 2005. Considering the example of a university hospital, the individual cost of each intervention is calculated and correlated with reimbursements by G-DRG2005 and so-called ''ambulant operation'' (EBM200plus). With these data, profits and losses are calculated for both in- and outpatient care. Results: Radiologic interventions of inpatients yield a profit in the majority of cases. With a base rate of 2900 Euro, the profits in our university hospital range between -872 Euro and +3411 Euro (mean: +1348 Euro). On the other hand, those angiographic interventions suitable for ''ambulant operation'' generate average profits of +372 Euro, if only direct costs are considered. The data of outpatient radiological interventions average between 381 Euro up to 1612 Euro lower than compared with profits obtained from in patient care. (orig.)

Radiological aerial monitoring in a nuclear emergency

International Nuclear Information System (INIS)

Shin, Hyeongki; Kim, Juyoul; Jung, Gunhyo

2008-01-01

Since North Korea announced the underground nuclear test on last October 9th, 2006, many countries around the world have worried about the atmospheric dispersion and pollution of radioactive materials crossing the border by the clandestine nuclear test. After that time, verifying the existence of nuclear test by detecting radioactive materials such as xenon, I-131, and Cs-134 at the early stage of radiological emergency, locating the position of test site by backward trajectory analysis, and chasing the moving path of airborne radionuclide have been heavily issued. And collection of airborne radioactivity and gamma radiation monitoring technology using an aircraft have been recently examined by an authority concerned in South Korea. Although various techniques of radiological aerial monitoring have been developed and operated around the world, the relevant technical development or research is still required. In order to decide potential measuring location and time within the framework of radiological monitoring system, we use HYSPLIT (Hybrid Single Particle Lagrangian Integrated Trajectory) model developed by National Oceanic and Atmospheric Administration (NOAA) of U.S. Department of Commerce. The model is validated and assessed against North Korea's nuclear test. Calculation results of radionuclide trajectory show a good agreement with measured values. Backward trajectory analysis is useful to track the radiological source term, possible time and place of nuclear accidents and/or activities. Nationwide early warning system using aircraft and atmospheric dispersion model can help a nearly real-time forecasting and warning in preparation for radiological emergencies. (author)

Calculations of the radiological impact of disposal of unit activity of selected radionuclides for use in waste management system studies

International Nuclear Information System (INIS)

Smith, G.M.

1985-03-01

The purpose of the work described is to provide estimates of the radiological impact following disposal of unit activity via each of several options, including shallow burial, engineered trench disposal, disposal in a geologic repository and disposal on the deep ocean bed. Results are presented for a range of important representative radionuclides. No single option is clearly the best from the radiological point of view. However, in conjunction with waste inventory data the results may be used to provide a preliminary view of the relative radiological merits of the various disposal options. (author)

Radiologic evaluation of facial injury; Avaliacao radiologica dos traumatismos faciais

Energy Technology Data Exchange (ETDEWEB)

Souza, Ricardo Pires de; Volpato, Richard [Complexo Hospitalar Heliopolis, Sao Paulo, SP (Brazil). Servico de Diagnostico por Imagem]. E-mail: richard_volpato@uol.com.br; Nascimento, Lia Paula [Complexo Hospitalar Heliopolis, Sao Paulo, SP (Brazil)

2003-03-01

A detailed radiological investigation of the maxillofacial injuries is essential to achieve good treatment results. The images should identify every lesion and guide the treatment, thus improving esthetic and functional results. With the aim of simplifying the diagnostic task, the face may be seen as a five regions structure that may suffer a regional fracture or combined fractures involving the adjacent regions. These regions represent areas of focus for pre surgical planning and are as follows: nasal, orbital, zygomatic, maxillary, and mandibular. In order to understand the injury mechanisms and their consequences it is useful to know the supporting buttresses, which are divided in five sagittal planes, three horizontal planes and two coronal planes. We reviewed the cases of patients with facial trauma treated at Complexo Hospitalar Heliopolis, Sao Paulo, Brazil. A review of the relevant issues concerning radiological investigation of these injuries is presented. This study allowed standardization and ordering of the radiological investigation in patients with facial trauma. (author)

PARATI - a dynamic model for radiological assessments in urban areas. Pt. 1. Modelling of urban areas, their contamination and radiation fields

International Nuclear Information System (INIS)

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

1996-01-01

The structure and mathematical model of PARATI, a detailed computer programme developed for the assessment of the radiological consequences of an accidental contamination of urban areas, is described with respect to the scenarios used for the estimation of exposure fields in a village or town, the models for the initial and secondary contamination with the radionuclide 137 Cs, the concepts for calculating the resulting radiation exposures and the changes with time of the contamination and radiation fields. Kerma rates at various locations in tropical urban areas are given, and the contribution of different contaminated surfaces to these rates after dry or wet deposition are discussed. (orig.). With 6 figs., 12 tabs

A graphical user interface for diagnostic radiology dosimetry using Monte Carlo (MCNP) simulation

International Nuclear Information System (INIS)

Collins, P.J.; Gorbatkov, D.; Schultz, F.W.

2000-01-01

Monte Carlo methods (for example, MCNP, EGGS4) are the 'gold standard' for both external and internal dosimetry in humans. These powerful simulation tools are, however, general-purpose codes and consequently do not provide a simple user interface for specific dosimetry tasks. We have developed a graphical user interface, for external radiation dosimetry (diagnostic radiology) using MCNP and an anthropomorphic mathematical phantom (Adam/Eva), which enables convenient modification and processing of the MCNP input and output files. The input form displays a colour coded, 3D representation of the phantom with a superimposed 'beam' for the required x-ray projection. The phantom can be rotated through 360 degrees and a transverse section at the level of the mid-point of the beam is also displayed. Text fields enable entry of input data (beam dimensions, source position, kVp, total filtration, focus-to-skin distance). A pull-down menu enables the user to select from 22 standard radiographic views. A standard projection can be modified, or new projection data entered if required. The input program modifies the MCNP input file and initiates processing. An output form displays the organ doses, normalised to unit skin entrance dose (with backscatter) (SED). The user can also enter the SED (calculated or measured) for a particular machine, to obtain the effective dose. To validate the program, the results for a PA Chest study (80 kVp, 2.5 mm Al total filtration) were compared with NRPB data (Jones and Wall, 1985). In conclusion, a convenient and reliable graphical user interface has been developed for MCNP, which enables dosimetry calculation for a full range of diagnostic radiological studies. (author)

Radiological protection report 2012

International Nuclear Information System (INIS)

2013-06-01

measurements. In addition, the Swiss Federal Office of Public Health publishes environmental monitoring data in its Annual Report. For the purpose of monitoring environmental radioactivity, ENSI operates a network that automatically monitors dose rates in the vicinity of nuclear power plants. The results are made available to the Swiss National Emergency Operations Centre, the Ministry of the Environment in Baden-Wuerttemberg and the European Radiological Data Exchange Platform. In 2012 emissions from Swiss nuclear facilities are similar to those in previous years and in the immediate vicinity of nuclear facilities the annual dose is less than 10μSv. However, the water-borne releases of radiation from the Muehleberg nuclear power station, unlike those at other nuclear facilities, continue to be so high that further remedial measures are required. In the field of dispersion, hourly simulations are calculated for all locations in the vicinity of a nuclear power station. They are based on current 3D wind speeds as provided by MeteoSwiss with a spatial resolution of 2 km. These calculations, together with the annual aero-radiometric test flights, are a valuable and precise tool that can be used at any time to analyse the current situation and forecast the development of radiation

The characteristics of radiological cloud caused by 'dirty bomb' attack

International Nuclear Information System (INIS)

Wang Qingbo; Wang Bairong

2006-01-01

This paper discusses the characteristics of the radiological cloud after the RDD explosion, including the initial cloud size, material's distribution and the rate of particle or aerosol sedimentation. For there are limited papers in involved this topic publicly, only empirical formulas are given. However, it would be helpful when evaluating the consequences of the RDD terrorism attacks. (authors)

The atolls of Mururoa and Fangataufa (French Polynesia). The nuclear testings. Radiological aspects

International Nuclear Information System (INIS)

Martin, G.

2007-01-01

This report provides a review of the radiological measures implemented during the thirty year period of French nuclear tests in Polynesian atolls of Mururoa and Fangataufa. It presents full details of the practices deployed throughout these tests, including, in particular, aspects concerning radiological protection for the population and the environment. It contains all the scientific results and measurements of radioactivity performed during this period, providing concrete facts that can be used to assess the consequences these tests have had on the personnel involved, the population and the environment. (author)

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

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-12-15

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

Radiology research in mainland China in the past 10 years: a survey of original articles published in Radiology and European Radiology

International Nuclear Information System (INIS)

Zhang, Long Jiang; Wang, Yun Fei; Yang, Zhen Lu; Lu, Guang Ming; Schoepf, U.J.; Xu, Jiaqian; Li, Enzhong

2017-01-01

To evaluate the features and trends of Radiology research in Mainland China through bibliometric analysis of the original articles published in Radiology and European Radiology (ER) between 2006 and 2015. We reviewed the original articles published in Radiology and ER between 2006 and 2015. The following information was abstracted: imaging subspecialty, imaging technique(s) used, research type, sample size, study design, statistical analysis, study results, funding declarations, international collaborations, number of authors, department and province of the first author. All variables were examined longitudinally over time. Radiology research in Mainland China saw a substantial increase in original research articles published, especially in the last 5 years (P < 0.001). Within Mainland China's Radiology research, neuroradiology, vascular/interventional Radiology, and abdominal Radiology were the most productive fields; MR imaging was the most used modality, and a distinct geographic provenience was observed for articles published in Radiology and ER. Radiology research in Mainland China has seen substantial growth in the past 5 years with neuroradiology, vascular/interventional Radiology, and abdominal Radiology as the most productive fields. MR imaging is the most used modality. Article provenience shows a distinct geographical pattern. (orig.)

Radiology research in mainland China in the past 10 years: a survey of original articles published in Radiology and European Radiology

Energy Technology Data Exchange (ETDEWEB)

Zhang, Long Jiang; Wang, Yun Fei; Yang, Zhen Lu; Lu, Guang Ming [Medical School of Nanjing University, Department of Medical Imaging, Jinling Hospital, Nanjing, Jiangsu (China); Schoepf, U.J. [Medical School of Nanjing University, Department of Medical Imaging, Jinling Hospital, Nanjing, Jiangsu (China); Medical University of South Carolina, Division of Cardiovascular Imaging, Department of Radiology and Radiological Science, Charleston, SC (United States); Xu, Jiaqian [Medical University of South Carolina, Division of Cardiovascular Imaging, Department of Radiology and Radiological Science, Charleston, SC (United States); Li, Enzhong [National Natural Science Foundation of China, Department of Medical Science, Beijing (China)

2017-10-15

To evaluate the features and trends of Radiology research in Mainland China through bibliometric analysis of the original articles published in Radiology and European Radiology (ER) between 2006 and 2015. We reviewed the original articles published in Radiology and ER between 2006 and 2015. The following information was abstracted: imaging subspecialty, imaging technique(s) used, research type, sample size, study design, statistical analysis, study results, funding declarations, international collaborations, number of authors, department and province of the first author. All variables were examined longitudinally over time. Radiology research in Mainland China saw a substantial increase in original research articles published, especially in the last 5 years (P < 0.001). Within Mainland China's Radiology research, neuroradiology, vascular/interventional Radiology, and abdominal Radiology were the most productive fields; MR imaging was the most used modality, and a distinct geographic provenience was observed for articles published in Radiology and ER. Radiology research in Mainland China has seen substantial growth in the past 5 years with neuroradiology, vascular/interventional Radiology, and abdominal Radiology as the most productive fields. MR imaging is the most used modality. Article provenience shows a distinct geographical pattern. (orig.)

Radiological protection in interventional radiology

International Nuclear Information System (INIS)

Padovani, R.

2001-01-01

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

Limits of the comparison between radiological and chemical hazards

International Nuclear Information System (INIS)

Maximilien, R.; Bounolleau, B.

2003-01-01

The primary reason for comparing radiological and chemical hazards is, in the absence of knowledge of similarities between underlying mechanisms, the comparability of the methods used to evaluate their long-term consequences, especially at low doses: carcinogenicity, mutagenicity and effects on reproduction. For radiations, the evaluation is performed above all in terms of risk quantification while for chemicals hazard identification is the main concern. (authors)

Effects of spent fuel types on offsite consequences of hypothetical accidents

International Nuclear Information System (INIS)

Courtney, J. C.; Dwight, C. C.; Lehto, M. A.

2000-01-01

Argonne National Laboratory (ANL) conducts experimental work on the development of waste forms suitable for several types of spent fuel at its facility on the Idaho National Engineering and Environmental Laboratory (INEEL) located 48 km West of Idaho Falls, ID. The objective of this paper is to compare the offsite radiological consequences of hypothetical accidents involving the various types of spent nuclear fuel handled in nonreactor nuclear facilities. The highest offsite total effective dose equivalents (TEDEs) are estimated at a receptor located about 5 km SSE of ANL facilities. Criticality safety considerations limit the amount of enriched uranium and plutonium that could be at risk in any given scenario. Heat generated by decay of fission products and actinides does not limit the masses of spent fuel within any given operation because the minimum time elapsed since fissions occurred in any form is at least five years. At cooling times of this magnitude, fewer than ten radionuclides account for 99% of the projected TEDE at offsite receptors for any credible accident. Elimination of all but the most important nuclides allows rapid assessments of offsite doses with little loss of accuracy. Since the ARF (airborne release fraction), RF (respirable fraction), LPF (leak path fraction) and atmospheric dilution factor (χ/Q) can vary by orders of magnitude, it is not productive to consider nuclides that contribute less than a few percent of the total dose. Therefore, only 134 Cs, 137 Cs- 137m Ba, and the actinides significantly influence the offsite radiological consequences of severe accidents. Even using highly conservative assumptions in estimating radiological consequences, they remain well below current Department of Energy guidelines for highly unlikely accidents

Comparison of time-oriented cost accounting catalogs to control a Departement of Radiology

International Nuclear Information System (INIS)

Hacklaender, T.; Mertens, H.; Cramer, B.M.

2005-01-01

Purpose: Within a hospital, the radiology department has taken over the role of a cost center. Cost accounting can be applied to analyze the cost for the performance of services. By assigning the expenditures of resources to the service, the cash value can directly be distributed to the costs of equipment, material and rooms. Time-oriented catalogs of services are predefined to calculate the number of the employees for a radiology department. Using our own survey of time data, we examined whether such catalogs correctly represent the time consumed in a radiology department. Only services relevant for the turnover were compared. Materials and Methods: For 96 primary radiological services defined by the score-oriented German fee catalog for physicians (Gebuehrenordnung fuer Aerzte), a ranking list was made for the annual procedures in descending frequency order. According to the Pareto principle, the 11 services with the highest frequency were chosen and the time consumed for the technical and medical services was collected over a period of 2 months. This survey was compared with the time-oriented catalogs TARMED and EBM 2000plus. Results: The included 11 relevant radiological services represented 80.3% of the annual procedures of our radiology department. When comparing the technical services between the time-oriented catalogs and our own survey, TARMED gives a better description of the time consumed in 7 of the 11 services and EMB 2000plus in 3 services. When comparing the medical services, TARMED gives a better description of the time consumed in 6 of the 11 services and EBM 2000plus in 4 services. When averaging all the radiological services, TARMED overestimates the current number of physicians necessary for primary reading by a factor of 10.0% and EBM 2000plus by a factor of 2.6%. Conclusion: As to the time spent on performing the relevant radiological services. TARMED is slightly superior to describe the radiology department of a hospital than EBM 2000plus

MTR radiological database for SRS spent nuclear fuel facilities

International Nuclear Information System (INIS)

Blanchard, A.

2000-01-01

A database for radiological characterization of incoming Material Test Reactor (MTR) fuel has been developed for application to the Receiving Basin for Offsite Fuels (RBOF) and L-Basin spent fuel storage facilities at the Savannah River Site (SRS). This database provides a quick quantitative check to determine if SRS bound spent fuel is radiologically bounded by the Reference Fuel Assembly used in the L-Basin and RBOF authorization bases. The developed database considers pertinent characteristics of domestic and foreign research reactor fuel including exposure, fuel enrichment, irradiation time, cooling time, and fuel-to-moderator ratio. The supplied tables replace the time-consuming studies associated with authorization of SRS bound spent fuel with simple hand calculations. Additionally, the comprehensive database provides the means to overcome resource limitations, since a series of simple, yet conservative, hand calculations can now be performed in a timely manner and replace computational and technical staff requirements

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

Health consequences [of the Chernobyl accident

International Nuclear Information System (INIS)

Ramoutar, S.

1996-01-01

The World Health Organisation Conference on the Health Consequences of the Chernobyl and Other Radiological Accidents, held in Geneva last November, is reported. The lack of representation from the civil nuclear industry led often to one-sided debates instigated by the anti-nuclear lobbies present. Thyroid cancer in children as a result of the Chernobyl accident received particular attention. In Belarus, 400 cases have been noted, 220 in Ukraine and 60 in the Russian Federation. All have been treated with a high degree of success. The incidence of this cancer would be expected to follow the fallout path as the main exposure route was ingestion of contaminated foods and milk products. It was noted that the only way to confirm causality was if those children born since the accident failed to show the same increased incidence. Explanations were offered for the particular susceptibility of children to thyroid cancer following exposure to radiation. Another significant cause of concern was the health consequences to clean-up workers in radiological accidents. The main factor is psychological problems from the stress of knowing that they have received high radiation doses. A dramatic increase in psychological disorders has occurred in the Ukraine over the past ten years and this is attributed to stress generated by the Chernobyl accident, compounded by the inadequacy of the public advice offered at the time and the socio-economic uncertainties accompanying the breakup of the former USSR. (UK)

General Employee Radiological Training and Radiological Worker Training: Program management manual

International Nuclear Information System (INIS)

1992-10-01

This manual defines and describes the DOE General Employee Radiological Training (GERT) and Radiological Worker I and II (RW I and II) Training programs. It includes material development requirements, standards and policies, and program administration. This manual applies to General Employee Radiological Training and Radiological Worker Training at all DOE contractor sites. The training materials of both GERT and RW I and II training reflect the requirements identified in the DOE Radiological Control Manual and DOE Order 5480.11. The training programs represent the minimum requirement for the standardized core materials. Each contractor shall implement the program in its entirety and may augment the standardized core materials to increase the general employee and radiological worker level of competency

Reconciling quality and cost: A case study in interventional radiology

International Nuclear Information System (INIS)

Zhang, Li; Mahnken, Andreas; Domroese, Sascha

2015-01-01

To provide a method to calculate delay cost and examine the relationship between quality and total cost. The total cost including capacity, supply and delay cost for running an interventional radiology suite was calculated. The capacity cost, consisting of labour, lease and overhead costs, was derived based on expenses per unit time. The supply cost was calculated according to actual procedural material use. The delay cost and marginal delay cost derived from queueing models was calculated based on waiting times of inpatients for their procedures. Quality improvement increased patient safety and maintained the outcome. The average daily delay costs were reduced from 1275 EUR to 294 EUR, and marginal delay costs from approximately 2000 EUR to 500 EUR, respectively. The one-time annual cost saved from the transfer of surgical to radiological procedures was approximately 130,500 EUR. The yearly delay cost saved was approximately 150,000 EUR. With increased revenue of 10,000 EUR in project phase 2, the yearly total cost saved was approximately 290,000 EUR. Optimal daily capacity of 4.2 procedures was determined. An approach for calculating delay cost toward optimal capacity allocation was presented. An overall quality improvement was achieved at reduced costs. (orig.)

Reconciling quality and cost: A case study in interventional radiology

Energy Technology Data Exchange (ETDEWEB)

Zhang, Li; Mahnken, Andreas [University Hospital Giessen and Marburg, Philipps University of Marburg, Department of Diagnostic and Interventional Radiology, Baldinger Strasse, Marburg (Germany); Domroese, Sascha [University Hospital Giessen and Marburg, Philipps University of Marburg, Division of Controlling, Baldinger Strasse, Marburg (Germany)

2015-10-15

To provide a method to calculate delay cost and examine the relationship between quality and total cost. The total cost including capacity, supply and delay cost for running an interventional radiology suite was calculated. The capacity cost, consisting of labour, lease and overhead costs, was derived based on expenses per unit time. The supply cost was calculated according to actual procedural material use. The delay cost and marginal delay cost derived from queueing models was calculated based on waiting times of inpatients for their procedures. Quality improvement increased patient safety and maintained the outcome. The average daily delay costs were reduced from 1275 EUR to 294 EUR, and marginal delay costs from approximately 2000 EUR to 500 EUR, respectively. The one-time annual cost saved from the transfer of surgical to radiological procedures was approximately 130,500 EUR. The yearly delay cost saved was approximately 150,000 EUR. With increased revenue of 10,000 EUR in project phase 2, the yearly total cost saved was approximately 290,000 EUR. Optimal daily capacity of 4.2 procedures was determined. An approach for calculating delay cost toward optimal capacity allocation was presented. An overall quality improvement was achieved at reduced costs. (orig.)

Presentation of evolutions of the CERES platform used to evaluate the consequences of the emissions of pollutants in the environment

Energy Technology Data Exchange (ETDEWEB)

Monfort, M.; Patryl, L.; Armand, P. [Commissariat a l' energie atomique et aux energies alternatives - CEA (France)

2014-07-01

The Radiological and Chemical Impact Laboratory (LIRC) of the French Atomic Energy Commission (CEA) is in charge of the development of modelling tools to evaluate the consequences on human health of releases of radionuclides or toxic chemicals in the environment, for emergency planning and for safety evaluation. In this context, the laboratory has developed the CERES application (Code d'Evaluations Rapides Environnementales et Sanitaires), in order that all impact calculations relative to CEA installations will be done using the same tools and methods. It is used to evaluate the consequences on human health of releases of isotopes in the environment, either for emergency planning or for safety evaluation. Various types of emissions can be simulated: atmospheric accidental emission, atmospheric emission during normal operation or emission in liquid media under normal operation. This application is used for emergency situations planning and for the realization of assessment calculations within a regulatory framework, for example in the safety documents relative to nuclear installations. It helps to evaluate either the consequences of accidental situations supposed to occur on installations or the impact of routine releases from single installations or nuclear sites on their near environment. A specific module is used to evaluate the dispersion and impact of tritium release and in normal situations for C-14 release. The ERASTEM module helps to estimate the release to environment in case of accidental situation on nuclear reactor. Two versions exist, one devoted to radiological impact evaluations, the other one devoted to toxic impact. This platform is used on every CEA site, either for emergency situation and impact studies on human health. Recent evolutions of these platforms follow demands expressed in CEA user's group. According to radiological version, these evolutions mainly concern the implementation of isotopes and the evaluation of atmospheric

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

International Nuclear Information System (INIS)

Genkel, Simone; Schnadt, Horst

2010-01-01

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

Cost calculations for decommissioning and dismantling of nuclear research facilities

International Nuclear Information System (INIS)

Andersson, I.; Backe, S.; Cato, A.; Lindskog, S.; Efraimsson, H.; Iversen, Klaus; Salmenhaara, S.; Sjoeblom, R.

2008-07-01

Today, it is recommended that planning of decommission should form an integral part of the activities over the life cycle of a nuclear facility (planning, building and operation), but it was only in the nineteen seventies that the waste issue really surface. Actually, the IAEA guidelines on decommissioning have been issued as recently as over the last ten years, and international advice on finance of decommissioning is even younger. No general international guideline on cost calculations exists at present. This implies that cost calculations cannot be performed with any accuracy or credibility without a relatively detailed consideration of the radiological prerequisites. Consequently, any cost estimates based mainly on the particulars of the building structures and installations are likely to be gross underestimations. The present study has come about on initiative by the Swedish Nuclear Power Inspectorate (SKI) and is based on a common need in Denmark, Finland, Norway and Sweden. The content of the report may be briefly summarised as follows. The background covers design and operation prerequisites as well as an overview of the various nuclear research facilities in the four participating countries: Denmark, Finland, Norway and Sweden. The purpose of the work has been to identify, compile and exchange information on facilities and on methodologies for cost calculation with the aim of achieving an 80 % level of confidence. The scope has been as follows: 1) to establish a Nordic network 2) to compile dedicated guidance documents on radiological surveying, technical planning and financial risk identification and assessment 3) to compile and describe techniques for precise cost calculations at early stages 4) to compile plant and other relevant data A separate section is devoted in the report to good practice for the specific purpose of early but precise cost calculations for research facilities, and a separate section is devoted to techniques for assessment of cost

Cost calculations for decommissioning and dismantling of nuclear research facilities

Energy Technology Data Exchange (ETDEWEB)

Andersson, I. (Studsvik Nuclear AB (Sweden)); Backe, S. (Institute for Energy Technology (Norway)); Cato, A.; Lindskog, S. (Swedish Nuclear Power Inspectorate (Sweden)); Efraimsson, H. (Swedish Radiation Protection Authority (Sweden)); Iversen, Klaus (Danish Decommissioning (Denmark)); Salmenhaara, S. (VTT Technical Research Centre of Finland (Finland)); Sjoeblom, R. (Tekedo AB, (Sweden))

2008-07-15

Today, it is recommended that planning of decommission should form an integral part of the activities over the life cycle of a nuclear facility (planning, building and operation), but it was only in the nineteen seventies that the waste issue really surface. Actually, the IAEA guidelines on decommissioning have been issued as recently as over the last ten years, and international advice on finance of decommissioning is even younger. No general international guideline on cost calculations exists at present. This implies that cost calculations cannot be performed with any accuracy or credibility without a relatively detailed consideration of the radiological prerequisites. Consequently, any cost estimates based mainly on the particulars of the building structures and installations are likely to be gross underestimations. The present study has come about on initiative by the Swedish Nuclear Power Inspectorate (SKI) and is based on a common need in Denmark, Finland, Norway and Sweden. The content of the report may be briefly summarised as follows. The background covers design and operation prerequisites as well as an overview of the various nuclear research facilities in the four participating countries: Denmark, Finland, Norway and Sweden. The purpose of the work has been to identify, compile and exchange information on facilities and on methodologies for cost calculation with the aim of achieving an 80 % level of confidence. The scope has been as follows: 1) to establish a Nordic network 2) to compile dedicated guidance documents on radiological surveying, technical planning and financial risk identification and assessment 3) to compile and describe techniques for precise cost calculations at early stages 4) to compile plant and other relevant data A separate section is devoted in the report to good practice for the specific purpose of early but precise cost calculations for research facilities, and a separate section is devoted to techniques for assessment of cost

Assessment of off-site consequences of nuclear accidents (MARIA)

International Nuclear Information System (INIS)

Haywood, S.M.

1985-01-01

A brief report is given of a workshop held in Luxembourg in 1985 on methods for assessing the off-site radiological consequences of nuclear accidents (MARIA). The sessions included topics such as atmospheric dispersion; foodchain transfer; urban contamination; demographic and land use data; dosimetry, health effects, economic and countermeasures models; uncertainty analysis; and application of probabilistic risk assessment results as input to decision aids. (U.K.)

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.

Digital radiology

International Nuclear Information System (INIS)

Dallas, W.J.

1990-01-01

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

Analytical probabilistic proton dose calculation and range uncertainties

Science.gov (United States)

Bangert, M.; Hennig, P.; Oelfke, U.

2014-03-01

We introduce the concept of analytical probabilistic modeling (APM) to calculate the mean and the standard deviation of intensity-modulated proton dose distributions under the influence of range uncertainties in closed form. For APM, range uncertainties are modeled with a multivariate Normal distribution p(z) over the radiological depths z. A pencil beam algorithm that parameterizes the proton depth dose d(z) with a weighted superposition of ten Gaussians is used. Hence, the integrals ∫ dz p(z) d(z) and ∫ dz p(z) d(z)2 required for the calculation of the expected value and standard deviation of the dose remain analytically tractable and can be efficiently evaluated. The means μk, widths δk, and weights ωk of the Gaussian components parameterizing the depth dose curves are found with least squares fits for all available proton ranges. We observe less than 0.3% average deviation of the Gaussian parameterizations from the original proton depth dose curves. Consequently, APM yields high accuracy estimates for the expected value and standard deviation of intensity-modulated proton dose distributions for two dimensional test cases. APM can accommodate arbitrary correlation models and account for the different nature of random and systematic errors in fractionated radiation therapy. Beneficial applications of APM in robust planning are feasible.

MEMO radiology

International Nuclear Information System (INIS)

Wagner-Manslau, C.

1989-01-01

This radiology volume is a concise handbook of imaging techniques, nuclear medicine, and radiation therapy, albeit that the main emphasis is on classic radiology. It offers, for instance, a survey of radiological findings for the most frequent pathological conditions, many overviews of differential diagnosis, a glossary of the technical bases of radiology and so forth. The contents are divided into the following chapters: Physical and biological bases; skeleton; thorax with the subdivisions lungs, heart, mediastinum, and pleura; gastrointestinal tract with the subsections esophagus, small and large intestine; liver; biliary tract; pancreas; retroperitoneal space; kidney; suprarenal glands; bladder; blood vessels, lymph nodes, spleen; mammary glands; female genitals; prostate and scrotum, epididymis and seminal vesicle. (orig./MG) With 23 figs [de

Study on Korean Radiological Emergency System-Care System- and National Nuclear Emergency Preparedness System Development

International Nuclear Information System (INIS)

Akhmad Khusyairi; Yudi Pramono

2008-01-01

Care system; Radiological Emergency Supporting System. Environmental radiology level is the main aspect that should be concerned deal with the utilization of nuclear energy. The usage of informational technology in nuclear area gives significant contribution to anticipate and to protect human and environment. Since 1960, South Korea has developed environment monitoring system as the effort to protect the human and environment in the radiological emergency condition. Indonesia has possessed several nuclear installations and planned to build and operate nuclear power plants (PLTN) in the future. Therefore, Indonesia has to prepare the integrated system, technically enables to overcome the radiological emergency. Learning from the practice in South Korea, the system on the radiological emergency should be prepared and applied in Indonesia. However, the government regulation draft on National Radiological Emergency System, under construction, only touches the management aspect, not the technical matters. Consequently, when the regulation is implemented, it will need an additional regulation on technical aspect including the consideration on the system (TSS), the organization of operator and the preparation of human resources development of involved institution. For that purpose, BAPETEN should have a typical independence system in regulatory frame work. (author)

Chemical and radiological vulnerability assessment in urban areas

Directory of Open Access Journals (Sweden)

Stojanović Božidar

2006-01-01

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

Reference radiology in nephroblastoma: accuracy and relevance for preoperative chemotherapy

International Nuclear Information System (INIS)

Schenk, J.P.; Schrader, C.; Zieger, B.; Ley, S.; Troeger, J.; Furtwaengler, R.; Graf, N.; Leuschner, I.

2006-01-01

Purpose: A reference radiologic diagnosis was carried out for the purpose of quality control and in order to achieve high diagnostic accuracy in the ongoing trial and study SIOP 2001/GPOH for renal tumors during childhood. The aim of the present study is to evaluate the value of diagnostic imaging and the benefit of reference evaluation at a pediatric radiology center. Materials and Methods: In 2004 the imaging studies of 97 patients suspected of having a renal tumor were presented at the beginning of therapy. Diagnostic imaging was compared to the primary imaging results and the histological findings and was analyzed in regard to the therapeutic consequence (primary chemotherapy without prior histology). 77 MRI, 35 CT and 67 ultrasound examinations of 47 girls and 50 boys (mean age 4 years; one day to 15.87 years old) were analyzed. In addition to the histological findings, the reference pathological results were submitted in 86 cases. Results from the primary imaging corresponding to the histology and results from the reference radiology corresponding to the histology and results from the reference radiology corresponding to the histology were statistically compared in a binomial test. Results: In 76 of the reference-diagnosed Wilms' tumors, 67 were confirmed histologically. In 72 cases preoperative chemotherapy was initiated. In 5 cases neither a Wilms' tumor nor a nephroblastomatosis was found. 16 of 21 cases (76%) with reference-diagnosed non-Wilms' tumors were selected correctly. The results of the primary imaging corresponded to the histology in 71 cases, and those of the reference radiology in 82 cases. The statistical evaluation showed that the results of the reference radiology were significantly better (p=0.03971). (orig.)

Off-site response for radiological emergencies

International Nuclear Information System (INIS)

Eldridge, J.S.; Oakes, T.W.; Hubbard, H.M.; Hibbitts, H.W.

1982-01-01

Environmental radiological surveillance under emergency conditions at off-site locations is one of the advisory functions provided by DOE within the ORO jurisdiction. The Department of Environmental Management of ORNL has been requested to provide sampling and analytical assistance at such emergency response activities. We have assembled and identified specific individuals and equipment to provide a rapid response force to perform field measurements for environmental radioactivity releases as a consequence of nuclear accidents. Survey teams for sample collection and field measurements are provided along with analytical assistance to operate the radioactivity measuring equipment in the DOE emergency van

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

International Nuclear Information System (INIS)

Zajacova, Z.

2009-01-01

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

Natural radiation - a perspective to radiological risk factors of nuclear energy production